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Forwards Draft Rev 4 of AP600 Certified Design Matl,Section 3.3, Buildings, as Requested by Staff in ITAAC Task Group Meeting on 980312
	ML20217D108
Person / Time
Site:	05200003
Issue date:	03/18/1998
From:	Mcintyre B; WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Quay T; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NSD-NRC-98-5625, NUDOCS 9803270313
	Download: ML20217D108 (46)
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' Westinghouse Energy Systems ggjp pennsywania 15230.osss Electric Corporation DCP/NRCl305 NSD-NRC-98-5625 Docket No.: 52-003

. March 18,1998 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555

%TTENTION: T. R. QUAY t UllJECT: RESPONSES TO STAFF REQUESTS REGARDlWG THE AP600 INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA (ITAAC)- REVISION 4 (DRAFT), SECTION 3.3, BUILDINGS

Dear Mr. Quay:

Enclosed is Revision 4 (Draf) of the AP600 Certified Design Material, Section 3.3, " Buildings," as requested the staff in the ITAAC Task Group Meeting on March 12,1998. This draft version of Revision 4 includes changes to Section 3.3 that have been incorporated as a result of responses to staff requests for additional information in regard to Revision 3 of the AP600 CDM of May 16,1998.

fext and tables that have been changed from Revision 3 are noted in the leR margin with vertical cl'ange bar Figures changes have been incorporated, but are not noted as changes on the figures, in additon, ia Table 3.3-6, item 1.g) has been added to correctly reflect an additional ITAAC as

c. mmitted in oer response to RAI 640.168, dated January 30,1998. RAI 640.185 from your letter dated March 6,1998 asked for clarification of this ITAAC.

Please contact Mr. Eugene J. Piplica at (412) 374-5310 if you have any questions concerning this trar.smittal. -

B~ /

lirian A. Mc ntyre, Manager p Advanced Plant Safety and Licensing

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ec: J. N. Wilson, NRC (1L,1E)

_ . N. J. Liparulo, Westinghouse (w/o Enclosures) [ _

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4 4 Certified Design Material

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BUILDINGS W" "@

E Revision: 4 (Draft) -

Effective: 3/16/98 3.3 Buildings Design Description i The Nuclear Island (NI) structures include the containment (the steel containment vessel and the I containment intemal stmeture) and the shield and auxiliary buildings. The containment, shield and auxiliary buildings are structurally integrated on a common basemat which is embedded below the finished I plant grade level. The containment vessel is a cylindrical welded steel vessel with elliptical upper and lower heads, supported by embedding a lower segment between the containment intemal structures concrete and the basemat concrete. The shield building, in conjunction with the internal structures of the containment building, provides shielding for the reactor coolant system and the other radioactive systems I and components housed in the containment. The shield building roof is a reinforced concrete structure I containing an integral, steel lined Passive Containment Cooling Water Storage (PCCWs) tank. The auxiliary building houses the safety-related mechanical and electrical equipment located outside the containment and shield buildings.

The annex building houses personnel access, technical support center, non lE electrical equipment, and hot machine shop. The radwaste building houses the low level waste processing and storage.

1. a) The NI structures are seismic Category I and are designed to withstand design basis loads, which I apply to the stmeture, without loss of stmetural integrity and safety function. The design bases I loads are those loads associated with:

1 I

Normal plant operation (including dead loads, live loads, lateral earth pressure loads, and i equipment loads, including hydrodynamic loads, temperature and equipment vibration);

I I

External events (including rain, snow, flood, tornado, tornado generated missiles and I earthquake); and i

I

Internal events (including flood, pipe mpture, equipment failure, and equipment failure I generated missiles).

i<

b) The top of the NI basemat is located below the design plant grade level per Table 3.3-1.

c) The containment and its penetrations are designed and constructed to ASME Code Section III, Class MC.'"

d) The containment and its penetrations retain their pressure boundary integrity associated with the design pressure, i

1. Cont.unment inclauon devices are addnssed in subsection 211. Cont;unnrnt System.

oAITAACS\rev4\it0303.wpf:0 1 98

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Certified Design Material o

BUILDINGS jM" -

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Revision: 4 (Draft) . -

Effective: 3/16/98 e) The containment and its penetrations maintain the containment leakage rate less than the maximum allowable leakage rate associated with the peak containment pressure for the design basis accident.

I f) The key features of the nuclear island structures are as defined on Table 3.3-5.

I I g) The containment shell provides a free volume and a heat transfer surface.

2. Selected walls of the NI buildings as defined on Table 3.3-1 provide shielding during noimal operations. The shield wall thicknesses of the NI buildings are defined on Table 3.3-1 except for designed openings or penetrations.

3. Selected walls of the annex building and the radwaste building as defined on Table 3.3-1 provide shielding during normal operations. The shield wall thicknesses of the annex building and the radwaste building are defined on Table 3.3-1 except for designed openings or penetrations.

4. a) Exterior walls and the basemat of the NI have a water barrier up to plant elevation 100 ft (design plant grade).

b) The boundaries between mechanical equipment rooms and the electrical and instrumentation and control (l&C) equipment rooms of the auxiliary building as identified in Table 3.3-2 are designed to prevent flooding of rooms that contain safety related equipment up to the maximum flood level for each room defined in Table 3.3-2. ,

c) The boundaries between the following rooms, which contain safety-related equipment - passive ,

core cooling system tPXS) valve / accumulator room A (11205), PXS valve / accumulator room B (11207), and chemical and volume system (CVS) room (11209)- are designed to prevent flooding between these rooms.

5. The radiologically controlled area of the auxiliary building at the Level 1 elevation contains adequate volume to contain the liquid volume of faulted liquid radwaste system (WLS) storage tanks. The available volume of the radiologically controlled area of the auxiliary building at the Level 1 elevation exceeds the volume of the liquid radwaste storage tanks.

6. a) Class IE cables and raceways are identified according to applicable color <oded Class IE divisions.

b) Class IE divisional cables are routed in their respective divisional raceways.

c) Separation is maintained between Class IE divisions and between Class IE divisions and non-Class IE cables in accordance with the fire areas as identified in Table 3.3-3.

d) Physical separation is maintained between Class 1E divisions and between Class IE divisions and non-Class IE cables.

3.3-2 UDM c:VTeACsvev49to303 wpf:031798 l

Certified Design Material l BUILDINGS :C ==

Revision: 4 (Draft) .

Effective: 3/16/98 _

7. Systems and components required for safe shutdown located in rooms identified in Table 3.3-4 are !

protected from the dynamic effects of postulated pipe breaks using pipe whip restraints. )

8. The reactor cavity sump has a minimum concrete thickness as shown on Table 3.3-1 between the bottom of the sump and the steel containment.

9. The shield building roof, passive containment cooling system (PCS) storage tank, and the fire water )

storage tank support and retain the PCS and fire water sources.

I 10. The constmetion approach or sequence is dependent on the soil characteristics as defined below: j i

1 . For hard soil sites with unconsolidated deposits with shear wave ve!ocities exceeding 2000 feet I per second, a review of the construction approach is not required.

I I . For soft soil sites with unconsolidated deposits with shear wave velocities in the range of 1000 i to 2000 feet per second, the constmetion approach will include two limits: i.) Shield building construction ahead of auxiliary building or ii.) Auxiliary building construction ahead of shield building.

Inspections, Tests, Analyses, and Acceptance Criteria l Table 3.3 5 specifies the inspections, tests, analyses, and associated acceptance criteria for the NI annex j i and radwaste buildings. I 3.3-3 W85fingh0US8 0:VTAACSVev4Vt0303wpf.031798

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4 BUILDINGS ;"5 7g Revision: 4 (Draft) - =i Effective: 3/16/98 Table 3.3 2 NI Building Room Boundaries Required to IIave Flood Barrier Floors and Walls Boundary /

Maximum Flood Level (inches) Between Room Number to Room Number Floor /36 12306 12211 Floor /3 12303 12203/12207 Floor /3 12313 12203/12207 12201/12202/12207 Floor /l 12300 12203/12204/12205 Floor /3 12312 12212 Wall /36 12306 12305 12301/12302/12303 Floor /l 12401 12312/12313 Wall /l 12401 12411/12412 Floor /36 12404 12304 Floor /12 12405 12305 Floor /36 12406 12306 Wall /36 12404 12401 Wall /l 12421 12452 Floor /3 12501 12401/12411/12412 Floor /3 12555 12421/12423/12422 Wall /36 12156/12158 12111/12112 3.3-17 W85tingh00$8 oNTAACS\rev4Vt0303.wpf.031798

Certified Design Material

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Flevision: 4 (Draft) - E Effective: 3/16/98 Table 3.3 3 Class IE Divisions in NI Fire Areas Class IE Divisions Fire Area Number A C B D 1200 AF 01 Yes Yes -

1200 AF 02 Yes Yes Yes -

1200 AF 03 - - Yes Yes 1200 AF 04 Yes Yes - -

1201 AF 02 - - Yes -

1201 AF 03 - - -

Yes 1201 AF 04 - - -

Yes 1201 AF 05 - -

Yes Yes 1

1201 AF 06 - -

Yes Yes {

1202 AF 03 -

Yes - -

1202 AF 04 Yes - - -

1204 AF 01 Yes - - -

1220 AF 01 - -

Yes Yes 1220 AF 02 - - -

Yes 1230 AF 01 Yes Yes - -

1 1242 AF 02 Yes -

Note: Dash (-) indwates not apphcable.

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d' Certified Design Material BUILDINGS Revision: 4 (Draft) -

Effective: 3/16/98 i Table 3.3-5 l Key Dimensions of NI Building Features i Reference Column Lines are Defined Relative to Containment Centerline i Reference Distance From Nominal Wall Inside Surface Distances and Tolerance on i Reference Containment Centerline Relationship to Reference Column Lines at Measured i Column (ft-in Elevation Level 1 Distance i Line North / South / East / West) (ft-in) ( in) 1 I 87 ft-6 in / East of Cont. CL. XI (Distance between Inside Surface of walls 1 at Col Ln.1 & N when Measured between 12 in l N On Containment Centerline Col I and 2) = 85 ft-0 in.

I Along N-S direction i J 69 ft-6 in East of Cont. CL. X2 (Distance between Inside Surface of walls 1 12in I at Col Ln.1 & J when Measured between Col 7.3 and i1) = 15 ft-0 in i K 51 ft-6 in East of Cont. CL. X3 (Distance between inside Surface of walls 12in I at Col Ln. J & K when Measured between Col 7.3 and 11) = 16 ft4 in i L 26 ft-0 in East of Cont. CL. X4 (Distance between inside Surface of walls i 12in I at Col Ln. K & L when Measured between Col 7.3 and iI) = 23 ft-6 in i M 8 ft-0 in East of Cont. CL. X5 (Distance between inside Surface of walls 12in I at Co Ln. L & M when Measured between Col 7.3 and 1I) = 16 ft-0 in i P 10 ft-0 in / West of Cont. CL. X6 (Distance between inside Surface of walls 212in I at Col Ln. M & P when Measured between Col 7.3 and i1) = 16 ft-0 in I Q 28 ft-0 in / West of Cont. CL. X7 (Distance between inside Surface of walls 2 12in I at Col Ln. P & Q when Measured between Col 7.3 and i1) = 15 ft-0 in l l 137 ft-0 in / South of Cont. X8 (Distance between Insik Surface of walls l CL at Col Ln.1 & 2 when Measured at interface z 12in 2 115 ft-0 in / South of Cont.

CL i 4 71 ft-0 in / South of Cont. CL X9 (Distance between Inside Surface of walls I at Col Ln.1 & 4 when Measured at interface : 12in with Col. I ) = 63 ft-0 in 3.3-21

[ W85tlngt10US8 oNTAACSvevet0303 wpf 031798

4 Certified Design Material BUILDINGS HE F

Flevision: 4 (Draft)

Effective: 3/16/98 1 Table 3.3 5 (cont.)

Key Dimensions of NI Building Features Reference Column Lines are Defined Relative to Containment Centerline Reference Distance From Nominal Wall Inside Surface Distances and Tolerance on Reference Containment Centerline Rela!!onship to Reference Col.amn Lines at Measured Column (ft in Elevation Level 1 Distance Line North / South / East / West) (ft in) (*in) 1 7.3 43 fi-9 in / North of Cont. CL X10 (Distance between Inside Surface of I walls at Col Ln. 7.3 & 1I when Measured at z 12in ii 117 fi-0 in / North of Cont. interface with Col. ! ) = 67 ft-9 in CL i 7 On Containment Centerline Xll [ Radial Distance from Center of + 15 in i Along East-West Direction Containment (Intersection of Col. Lines N - 3 in and 7) to Outside Surface of Shield Building when Measured along Col. Lines 7 and N) =

72 ft-6 in 1 -- --

X12 (Distance between Outside Surface of +3 ft I walls at Col Ln.1 & N when Measured at - 1 ft l Col. Line 1) = 91 ft-0 in 1 -- --

X13 (Distance From Outside Surface of wall +3 ft i at Col Ln. I to Col. Line 7 when Measured at -l ft I Col. Line !) = 138 ft-0 in I -- --

X14 (Distance From Outside Surface of wall +3 ft I at Col Ln. I1 to Col. Line 7 when Measured -l ft I at Col. Line I) = 118 ft-0 in X15 (Distance between Outside Surface of +3 ft I walls at Col Ln. I & Q when Measured at -l ft 1 Col. Line 1I) = 117 ft-6 in 1 -- --

X16 (Distance From Outside Surface of wall +3 ft I at Col Ln. Q to Col. Line N when Measured - 1 ft I at Col. Line 11) = 29 ft-0 in I -- --

X17 (Distance between Outside Surface of +3 ft I shield building wall to shield building -l ft I centerline when Measured betwsen Col.

I Lines N to Q) = 72 ft-6 in I -- -- X18 (Distance between shield building z 3 in I centerline to Reactor Vessel centerline when i Measured along Col. Line N in North-South I Direction) = 7 ft-6 in 3.3 22 M5NS8 oNTAACSvevWt0303 wpt:031798

e Certified Design Material BUILDINGS E: m Revision: 4 (Draft) -

Effective: 3/16/98 _

l Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria Design Cooitniement Inspections, Tests, Analyses Acceptance Criteria 1.a) The NI structures are An inspection of the as-built An inspection report exists that seismic Category I and are concrete thickness and concludes that the as-built designed to withstand design reinforcement cross-sectional area concrete and reinforcement i basis loads specified in the (density) (excluding designed quantities for the critical seismic I Design Description (Section 3.3 openings or penetrations will be Category I building sections I paragraph 1.a), which apply to the performed for the critical N1 defined on Table 3.3-1 were used structure, without loss of safety structural sections defined on during construction.

function. Table 3.3-1. This inspection data will be reconciled with the applicable structural section data defined on Table 3.3-1 which represents the required concrete and reinforcement to withstand the i design basis loads specified in the i Design Description (Section 3.3 l paragraph 1.a).

1.b) The top of the NI basemat inspection of the as-built nuclear The top of the NI basemat is is located below the design plant island basemat structure will be located below the design plant i level per Table 3.31. conducted. level consistent with the dimension defined on Table 3.3-1. I 1.c) The containment and its See Certified Design Material, See Certified Design Material, penetrations are designed and Subsection 2.2.1, Containment Subsection 2.2.1, Containment constructed to ASME Code System. System. 3 Section III, Class MC.'"

1.d) The containment and its See Certified Design Material, See Certined Design Material, penetrations retain their pressure Subsection 2.2.1, Containment Subsection 2.2.1. Containment l boundary integrity associated vith System. System. l the design pressure.

l.e) The containment and its See Certified Design Material, See Certified Design Material, penetrations maintain the Subsection 2.2.1. Containment Subsenion 2.2.1. Containment containment leakage rate less than System. System.

the maximum allowable leakage rate associated with the peak containment presse.re for the -

design basis accident.

I

1. Cont.unnrnt isolanon devices are addressed m subsection 2 2.1. Containnent System.

3.3-23 DDNS8 oMAACS\rev44t0303 wpf:031798

Certified Design Material BUILDINGS g" sg

" E Revision: 4 (Draft) -

Effective: 3/16/98 I Table 13-6 (cont.)

Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 1.f) De key features of Nuclear An inspection will be performed he as-built inspection repon i Island Structures are defined on of the as-built configuration of the exists and concludes that the key l Table 3.3-5. Nuclear Island Structures for key features of the Nuclear Island I features defined on Table 3.3-5. Structures are consistent with the I dimensions defined on i Table 3.3-5.

1 1.g) The containment shell The maximum containment shell The containment shell maximum I provides a free volume and a heat inside height from the operating inside height from the operating 1 transfer surface, deck is measured and the inner deck is 121*-1" (with tolerance of I radius below the spring line is +12", -6"), and the inside i measured at two orthogonal radial diameter is 130 feet nominal I directions at one elevation. (with tolerance of +12", -6").

2. Selected walls of the NI Inspection of the as-built NI The as-built inspection report buildings as defined on building wall thicknesses, exists and concludes that the Table 3.3-1 provide shielding identified on Table 3.3-1 will be shield walls of the NI buildings during normal operations. The performed. as defined on Table 3.3-1 are shield wall thicknesses of the consistent with the minimum NI buildings are defined on shield wall thicknesses defined Table 3.3-1 except for designed on Table 3.3-1.

openings or penetrations.

3. Selected walls of the annex Inspection of the as-built annex The as-built inspection report i I

building and the radwaste building building and the radwar,te building exists and concludes that the as defined on Table 3.3-1 provide wall thicknesses, identified on shield walls of the annex building shielding during normal Table 3.3-1 will be performed. and the radwaste building as operations. The shield wall defined on Table 3.3-1 are thicknesses of the annex building consistent with the minimum and the radwaste building are shield wall thicknesses defined j defined on Table 3.3-1 except for on Table 3.3-1.

designed openings or penetrations. l 4.a) Exterior walls and the Inspection of the as-built exterior An as-built inspection report exists basemat of the NI have a water walls and the basemat of the NI up that confirms that a water barrier barrier up to plant elevation 100 ft to plant elevation 100 ft, O in. for exists on the NI exterior walls up (design plant grade). application of water barrier will be to plant elevation of 100 ft and I performed during construction below the basemat.

before the walls are poured.

4.b) The boundaries between Inspection of the rooms identified An as-built inspection report roorns identined in Table 3.3 2 of in Table 3.3-2 will be performed exists that confirms Doors and the auxiliary building are designed to confirm that the Doors and wa!!s as identified on Table 3.3-2 to prevent nooding of rooms that walls prevent Hooding up to the have pro.isions to prevent contain safety related equipment. maximum Good level in the room. Gooding between rooms up to the maximum flood elevations.

3.3-24 U@ ISO oNTAACSWv%t0303.wpf:031798

Certified Design Material BUILDINGS HE -.

Revision: 4 (Draft) -

Effective: 3/16/98 _

l Table 3.3-6 (cont.)

Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment inspections Tests, Analyses Acceptance Criteria 4.c) The boundaries between the Inspection of the boundaries An as-built inspection report following rooms, which contain between the following rooms exists that confirms that safety-related equipment - PXS which contain safety-related provisions to prevent flooding are valve / accumulator room A equipment - PXS Valve / provided.

(11205), PXS valve / accumulator Accumulator Room A (11205),

room B (11207), and CVS room PXS Valve / Accumulator Room B (11209)- are designed to prevent (11207), and CVS Room flooding between these rooms. (11209)- will be performed to confirm that the floors and walls prevent flooding of the other rooms to a maximum flood level of 108 ft.

5. The as-built available volume Inspection will be performed of An as-built inspection report of the radiologically controlled the as-built radiologically exists and concludes that the area of the auxiliary building controlled area of the auxiliary available room volumes of the between Level I to Level 2 building between Level 1 to Level radiologically controlled area of elevations exceed the volume of 2 elevations to define volume. the auxiliary building at Level I the liquid radwaste storage tanks. exceed the volume of the liquid radwaste storage tanks. I 6.a) Class IE cables and raceways Inspections of the as-built Class Class IE cables and raceways are are identified according to IE cables and raceways will be identified by the appropriate color applicable color-coded Class IE conducted. code.

divisions.

6.b) Class IE divisional cables are Inspections of the as-built Class Class IE cables are routed in routed in their respective divisional IE divisional cables and raceways raceways assigned to the same l raceways. will be conducted. division. There ar'e'no other ' I I

safety division cables in a raceway assigned to a different division.

6.c ) Separation is maintained Inspections of the as-built Results of the inspection will j between Class IE divisions and Class IE division cables and confirm that the separation between Class IE divisions and raceways located in the fire areas between Class IE divisions is l I non-Class IE cables in accordance identified in Table 3.3-3 will be consistent with Table 3.3-3. i with the fire areas as identified in conducted.

1 Table 3.3 3.

I l

3.3-25 W .-. N8 NIM 88 oNTAACSVev4Mt0303 wpf 031798 l

l

. . . . _ _ . ._ ____________J

a Certified Design Material BUILDINGS = E W

Flevision: 4 (Draft) .

Effective: 3/16/98 i Table 3.3-6 (cont.)

Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests. Analyses Acceptance Criteria 6.d) Physical separation is inspections of the as-built Class Results of the inspection will maintained between Class IE lE raceways will be performed to confirm that the separation divisions and between Class IE confirm that the separation between Class lE raceways of divisions and non-Class IE cables, between Class IE raceways of different divisions and between different divisions and between Class IE raceways and non-Class Class IE raceways and non-Class IE raceways is consistent with the IE raceways is consistent with the followings:

following:

- Within the main control room - Within the main control room and remote shatdown area, the and remote shutdown area, minimum vertical separation is the vertical separation is 3 inches and the minimum 3 inches or more and the horizontal separation is 1 inch. horizontal separation is 1 inch or more. 1

- Within other plant areas - Within other plant areas (limited hazard areas), the (limited hazard areas), the minimum separation is defined separation meets one of the by one of the following: following: .

I 1

I) The minimum vertical 1) The vertical separation is j separation is 5 feet and 5 feet or more and the I the minimum horizontal horizontal separation is ;

separation is 3 feet. 3 f,eet or more except. l l

2) The minimum vertical 2) The minimum vertical separation is 12 inches separation is 12 inches and the minimum and the minimum horizontal separation is horizontal separation is 6 inches for raceways 6 inches for raceways containing only containing only instrumentation and instrumentation and control and low. voltage control and low voltage power cables <2/0 AWG. power cables <2/0 AWG.

l 3.3-26 MIIMS8 o:vTAACSVev4Vt0303 wpf.031798

r Certified Design Material e

BUILDINGS ME 9E 9

Revision: 4 (Draft)

Effective: 3/16/98 _

l Table 3.3-6 (cont.)

Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria

3) For configurations that 3) For configurations that involve exclusively involve exclusively limited energy content limited energy content cables (instrumentation cables (instrumentation and control), these and control), these minitrum distances are minimum distances are 3 inches and 1 inches 3 inches and I inch respectively. respectively.

4) For conHgurations 4) For configurations that involvmg an enclosed involve an enclosed

raceway and an open raceway and an open raceway, the minimum raceway, the minimum vertical separation is vertical separation is I inch if the enclosed I inch if the enclosed raceway is below the open raceway is below the raceway. raceway.

5) For conGguration 5) For configurations that involving enclosed involve enclosed raceway.

raceways. The minimum The minimum vertical separation is 1 inch in and horizontal separation both horizontal and is I inch.

sertical directions.

- Where rninimum separatiei - Where minimum separation distances are not maintained, distances are not met, the the circuits are run in enclosed circuits are run in enclosed raceways or barriers are raceways or barriers are provided. provided.

- Separation distances less than - A report exists and concludes I those speci6ed above and not that separation distances less I run in enclosed raceways or than those specified above i provided with barriers are and not provided with based on analysis, enclosed raceways or barriers have been analyzed.

3.3-27 W

W85tingh00S8 o:VTAACSvevWt0303 wpf;031798

i Certified Design Material BUILDINGS EE E M E Revision: 4 (Draft)

Effective: 3/16/98 I Table 3.3-6 (cont.)

Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria

- Non-Class IE wirir.g that is - Non-Class IE wiring that is not separated from Class IE or not separated from Class IE associated wiring by the or associated wiring by the minimum separation distance minimum separation distance I or by a barrier or analyzed is or by a barrier or analyzed is I considered as associated treated as Class IE wiring.

circuits and subject to Class IE requirements.

7. Systems and components An inspection will be performed of An as-built Pipe Rupture Hazard required for safe shutdown located the as-built high energy pipe break Analysis Report exists and i in rooms identified in Table 3.3-4 pipe whip restraints features for concludes that equipment required are protected from the dynamic systems located in rooms identified for safe shutdown located in i effects of postulated pipe breaks in Table 3.3-4 rooms identified in Table 3.3-4 using pipe whip restraints. can withstand the effects of postulated pipe rupture without loss of required safety function.

8. 'Ihe n. actor cavity sump has a Inspection of the as-built The as-built it.spection report ,

minirrum concrete thickness as containment building internal exists and concludes that the i shown in Table 3.3-1 between the structures will be performed. reactor cavity sump has a )

bottom t,f the sump ad the steel minimum concrete thickness as I shown on Table 3.3-1 between the I containment.

bottom of the sump and the steel containment.

9. The shield building roof, PCS Visual inspection of the PCS The as-built inspection report storage tank, and the fire water storage tank exterior tank exists and concludes that the storage tank support and retain the boundary and shield building water leakage does not exceed PCS and fire water sources. tension ring will be performed 100 gal /hr.

before and after filling of the PCS storage tank and fire water storage tank for significant water leakage

(>100 gal /hr as measured by water level change).

10. The construction approach for A visual inspection of the as-built The as-built inspection concludes soft soil sites includes two limits: auxiliary building, shield building, that the construction limits have and containment structures will be not been exceeded.

performed during construction to confirm that one of the two limits were met:

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Certified Design Material BUILDINGS gs =ig E i Revision: 4 (Draft) .

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Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria i.) Shield building construction i.) The north walls of the ahead of auxiliary building or auxiliary building are completed to elevation level 2 prior to placement of concrete in the shield building above elevation level 2 or in-containment structures above elevation level 2.

ii.) Auxiliary building construction ii.) The concrete was not placed ahead of shield building. in the auxiliary building above elevation level 4 before the shield building was completed to elevation level 2.

This commitment applies for )

only soft solid sites having !

unconsolidated deposits with shear wave velocities in the range from 1,000 to 2,000 feet per second.

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NSD-NRC-98-5625, Forwards Draft Rev 4 of AP600 Certified Design Matl,Section 3.3, Buildings, as Requested by Staff in ITAAC Task Group Meeting on 980312

Text

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NSD-NRC-98-5625, Forwards Draft Rev 4 of AP600 Certified Design Matl,Section 3.3, Buildings, as Requested by Staff in ITAAC Task Group Meeting on 980312

Text

Dear Mr. Quay:

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