ML052090038

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Attachment for the Summary of July 20, 2005 Meeting Between NRC and NEI, Cipims/Itaac Verification Demonstration Program, Phase I Report, Revision 0
ML052090038
Person / Time
Site: Nuclear Energy Institute
Issue date: 07/20/2005
From:
Westinghouse
To:
Electric Power Research Institute, Office of Nuclear Reactor Regulation, Nuclear Energy Institute
Kleeh E, NRR/DIPM/IIPB, 415-2964
References
Download: ML052090038 (37)
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Text

CIPIMS/ITAAC Verification Demonstration Program Phase 1 Report Revision 0 November 19, 2004 Status of Phase 2 Open Items - July 20, 2005 Westinghouse Electric Company For NEI and EPRI

CIPIMS/ITAAC Verification Demonstration Phase 1 Report NRC and the industry establish the following specific goals for the next phase.

1. Determine extent to which ITAAC and their precursor construction activities need to be identified in construction schedules.

Status: Done. An overall schedule will be made available by the project for NRC review. Applicant/licensee wvill address questions as necessary.

2. Establish process/criteria for determining documentation requirements for each ITAAC (ITAAC Determination Bases).

Status: In process discussions ongoing.

3. Determine format and content of licensee ITAAC determination letter to NRC.

Status: In process discussions ongoing.

4. Determine format and content of NRC ITAAC verification documentation, including 52.99 notices.

Status: In process discussions ongoing.

5. Determine required nature, extent and format for electronically available information to NRC, including construction schedule info, detailed design info and quality records (e.g.,

deviation reports).

Status: Project specific. Further discuss needed for to establish generic guidance.

6. Identify acceptable method(s) for licensee sharing of schedule information v/NRC to ensure compatibility with CIPIMS.

Status: Project specific. Part of item 1.

7. Jointly demonstrate the Construction Inspection and ITAAC Verification processes from order to "fuel load" with at least one current, real world example.

Status: In process discussions ongoing.

8. Determine when walkdowns are necessary to verify an ITAAC is met.

Status: In process discussions ongoing.

9. Clarify the meaning of "as-built" as used in ITAAC acceptance criteria.

Status: In process discussions ongoing. DCD Tier I defines as-built as: "As-built means the physical properties of a structure, system, or component following the completion of its installation or construction activities at its final location at the plant site."

CIPIMS/ITAAC Verification Demonstration Phase I Report

10. Establish ground rules for handling various types of ITAAC acceptance criteria, including 1) the "report exists and concludes" type of found in numerous individual ITAAC; and 2) acceptance criteria that indicate no documentation requirements, e.g.,

"Each check valve changes position as indicated in Table xyz."

Status: In process discussions ongoing. E.g. Workstream CVS5 discusses check valve position; E.g. CVS2 discusses "report exists and concludes."

SAAIPLEA -SIMPLIFIEDSUBMITTAL CASE:

ITAAC Completion Letter A for RVHII - ITAAC 2.1.3-2.2.c)

Date

Subject:

ITAAC 2.1.3-2.2.c) Completion Notice Mr._

Nuclear Regulatory Commission We have completed the a.n~

vnt of the reactor vessel arrangement, ITAAC 2.1.3-2.2.c) and have determined that the specific acceptance criterion for this ITAAC has been met.

The results of as-built measurements of the reactor vessel are in compliance with the requirements of ITAAC 2.1.3-2.2.c).

Outline and as-built drawings that form the basis for this conclusion are available at the plant site. We request NRC staff confirmation of this conclusion and publication of the required notice in the Federal Register per 10 CFR 52.99 and in accordance with the NPle process and schedule guidance for ITAAC completion, evaluation and notification..

Sincerely, Designated Licensee Officer or Manager

SAAIPLEB-AlORE DETAIL SUBAMTTAL CASE:

ITAAC Completion Lcttcr B for RVHI - ITAAC 2.1.3-2.2.c)

Date_

Subject:

ITAAC 2.1.3-2.2.c) Completion Notice Mr._

Nuclear Regulatory Commission We have completed the assessment of the reactor vessel arrangement, ITAAC 2.1.3-2.2.c) and have determined that the specific acceptance criterion for this ITAAC has been met.

The results of as-built measurements of the reactor vessel are in compliance with the requirements of ITAAC 2.1.3-2.2.c).

The bases for this conclusion include the documents identified below and are available at the plant site.

1. APP-MVO1 -VI -001 Rev. 3., API OOO Reactor Vessel Outline Elevation
2. APP-MV02-VI-002 Rev. 1, API000 Reactor Vessel Outline Plan
3. L5-ODA171 Rev. 1, APIOOO Reactor Vessel As-Built Drawing (I of 3)
4. L5-ODA172 Rev. 1, API OOO Reactor Vessel As-Built Drawing (2 of 3)
5. L5-ODA 173 Rev. 1, API OOO Reactor Vessel As-Built Drawing (3 of 3)

We request NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99 and in accordance with the NRC process and schedule guidance for ITAAC completion, evaluation and notification.

Sincerely, Designated Licensee Officer or Manager

I TARC-WoF<Sfi;E-.

Suggest to remove WSName WS Title Component ASME Code Status for the API000 CVS1 Chemical and Volume Control System Pipe weld ASME Code Status for the API000 CVS2 Chemical and Volume Control System Scismic Qualification of APIOOO Chemical and CVS3 Volume Control System Valves Make-up capability of the APIOOO Chemical and CVS4 Volume Control System Operation Check of API000 Chemical and Volume CVS5 Control System Valves RVH1 Reactor Vessel Head Arrangement ASME design and construction of API000 Reactor RVH2 Vessel Head RVH3 Reactor Internals Vibration STR1 Building Physical Arrangement STR2 Nuclear Island Critical Sections STR3 Fire Area Boundaries Building Waterproofing - basemat and exterior walls to STR4A grade STR4B Building Waterproofing - I&C flood boundaries STR4C Building Waterproofing - PXS, CVS flood boundaries A 4 14 ')I^C

7. -

Functional Arrangement of the ABWR Turbine Gland TGS1 Seal System TGS2 Turbine Gland Seal System Displays for the ABWR I &

lelV-

I

INSTRUMENTATION TUBE CRDM HOUSING INLET NOZZLE

-I-

"8" Figure 2.1.3-3 Reactor Vessel Arrangement

Table 2.1.3-4 Key Dimensions and Acceptable Variations of the ReactorVessel and Internals (Figure 2.1.3.2 and Figure 2.1.3-3)

Dimension Nominal Acceptable or Elevation Value Variation Description Cinches)

(inches)

(inches)

RV inside diameter at beitline (inside cladding)

A 157.0

+1.04-1.0 RV wall thickness at belgine (without cladding)

B 8.0

+1.0/-0.12 RVwall thickness at bottom head (without cladding)

C 6.0

+1.0/-0.12 RVirdet nozzle inside diameter at safe end D

22.0

+0.351-0.10 RV outlet nozzle inside diameter at safe end E

31.0

+0.35/-O.lO Elevation from RV mating surface to centerline of inlet F

62.5

+0.25/-0.25 nozzle Elevation from RV mating surface to centerline of outlet G

80.0

+0.251-0.25 nozzle Elevation from RV mating surface to centerline of direct H

100.0

+0.25/-0.25 vessel injection nozzle Elevation from RV mating surface to inside of RVbottom 1

397.59

+1.01-0.50 head (inside cladding)

Elevation from RVrnating surface to top of lower core J

327.3

+0.501-0.50 supportplate Separation distance between bottom of upper core plate K

189.8

+0.20/0.20 and top of lower core support with RV head in place

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Table 2.3.2-1 Class IE/

Loss of ASME Remotely Qual. for Safety-Motive Code Seismic Operated Harsh Related Control Active Power Equipment Name Tag No.

Section 1II Cat. I Valve Envir.

Display PMS Function Position RCS Purification Motor-CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer As Is operated Isolation Valve V00I (Valve Closed Position)

RCS Purification Motor-CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer As Is operated Isolation Valve V002 (Valve Closed Position)

RCS Purification Motor-CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer As Is operated Isolation Valve V003 (Valve Closed Position)

CVS Resin Flush Line CVS-PL-Yes Yes No

/

Containment Isolation Valve V040 CVS Resin Flush Line CVS-PL-Yes Yes No

/

Containment Isolation Valve V041 CVS Demineralizer Resin Flush CVS-PL-Yes Yes No Transfer Line Containment Isolation V042 Open/

Thermal Relief Valve Transfer Closed CVS Letdown Containment CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer Closed Isolation Valve V045 (Valve Closed Position)

CVS Letdown Containment CVS-PL-Yes Yes Yes Yes/No Yes Yes Transfer Closed Isolation Valve V047 (Valve Closed l_

Position)

Table 2.3.2-1 (cont.)

Class IE/

Loss of ASME Remotely Qual. for Safety-Motive Code Seismic Operated Harsh Related Control Active Power Equipment Name Tag No.

Section III Cat. I Valve Envir.

Display PMS Function Position CVS Purification Return Line CVS-PL-Yes Yes No

/

Transfer Pressure Boundary Check Valve V080 Closed CVS Purification Return Line CVS-PL-Yes Yes No

/

No Transfer Pressure Boundary Isolation V081 Closed Check Valve CVS Purification Return Line CVS-PL-Yes Yes No Transfer Pressure Boundary Check Valve V082 Closed CVS Auxiliary Pressurizer CVS-PL-Yes Yes Yes Yes/Yes No Yes Transfer Closed Spray Line Pressure Boundary V084 Closed Valve CVS Auxiliary Pressurizer CVS-PL-Yes Yes No Yes/Yes Transfer Spray Line Pressure Boundary V085 Closed Check Valve CVS Makeup Line Containment CVS-PL-Yes Yes Yes Yes/No Yes Yes Transfer As Is Isolation Motor-operated Valve V090 (Valve Closed Position)

CVS Makeup Line Containment CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer As Is Isolation Motor-operated Valve V091 (Valve Closed Position)

CVS Hydrogen Addition Line CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer Closed Containment Isolation Valve V092 (Valve Closed Position)

Table 2.3.2-1 (cont.)

l Class IE/

Loss of ASME Remotely Qual. for Safety-Motive lCode Seismic Operated Harsh Related Control Active Power Equipment Name Tag No.

Section III Cat. I Valve Envir.

Display PMS Function Position CVS Hydrogen Addition Line CVS-PL-V094 Yes Yes No

/

Transfer Containment Isolation Check Closed Valve CVS Makeup Line Containment CVS-PL-V100 Yes Yes No Transfer Isolation Thermal Relief Valve Open/

Transfer Closed CVS Demineralized Water CVS-PL-Yes Yes Yes Yes/No No Yes Transfer Closed Isolation Valve V136A Closed CVS Demineralized Water CVS-PL-Yes Yes Yes Yes/No No Yes Transfer Closed Isolation Valve V136B Closed

Table 2.3.2-2 Line Name Line Number ASME Code Section III F e ti9uiFLe.

_____i__

tVSS PBii~t~iiiRt WTXT Penetran Lne

oL03,

=s 9-is l

q0i

,7.

Line WBBULO5 CVS Supply Line to Regenerative Heat Exchanger BBD L002 No CVS Return Line from Regenerative Heat' BBD LOI8 No Exchanger BBD L073 No CVS Line from Regenerative Heat Exchanger to BBD L003 No Letdown Heat Exchanger BBD L072 No CVS Lines from Letdown Heat Exchanger to BBD L004 No Demin. Tanks BBD L005 No CVS Lines from Demin Tanks to RC Filters BBD L020 No BBD L021 No BBD L022 No BBD L029 No BBD L037 No CVS Lines from RC Filters to Regenerative Heat BBD L030 No Exchanger BBD L031 No BBD L034 No CVS Resin Fill Lines to Demin. Tanks BBD L008 No BBD L013 No BBD L025 No

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Requirement Inspection, Test or Analysis Acceptance Criteria ITAAC Determination Basis 3.b) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that the The NDE portions of the as-built ASME Code Design piping identified in Table 2.3.2-2 as boundary welds will be performed in ASME Code Section III requirements Report that apply to the items in Table 2.3.2-2.

ASME Code Section III meet ASME accordance with the ASME Code are met for non-destructive Code Section III requirements.

Section 111.

examination of pressure boundary welds.

Table 2.3.2-2 Line Name Line Number ASME Code Section III EVS PtrificationLiiiefRjtum

-fa8n__

Lie BB-L0O47 CVS Supply Line to Regenerative Heat Exchanger BBD L002 No CVS Return Line from Regenerative Heat BBD LO18 No Exchanger BBD L073 No CVS Line from Regenerative Heat Exchanger to BBD L003 No Letdown Heat Exchanger BBD L072 No CVS Lines from Letdown Heat Exchanger to BBD L004 No Demin. Tanks BBD L005 No CVS Lines from Demin Tanks to RC Filters BBD L020 No BBD L021 No BBD L022 No BBD L029 No BBD L037 No CVS Lines from RC Filters to Regenerative Heat BBD L030 No Exchanger BBD L031 No BBD L034 No CVS Resin Fill Lines to Demin. Tanks BBD L008 No BBD1L013 No BBD L025 No

'.14v.

Requirement J Inspection, Test or Analysis Acceptance Criteria ITAAC Determination Basis I

5. The seismic Category I equipment identified in Table 2.3.2 1 can withstand seismic design basis loads without loss of safety function.

i) Inspection will be performed to verify that the seismic Category I equipment identified in Table 2.3.2-1 is located on the Nuclear Island.

i) The seismic Category I equipment identified in Table 2.3.2 1 is located on the Nuclear Island.

As-built documents indicate the items in Table 2.3.2-1 are located on the nuclear isalnd.

ii) Type tests, analyses, or a ii) A report exists and concludes that The portions of the as-built ASME Code Design Report that combination of type tests and analyses the seismic Category I equipment can apply to the seismic capability of the items in Table 2.3.2-1.

of seismic Category I equipment will withstand seismic design basis be performed.

dynamic loads without loss of safety function.

iii) Inspection will be performed for the existence of a report verifying that the as-installed equipment including anchorage is seismically bounded by the tested or analyzed conditions.

iii) A report exists and concludes that the as-installed equipment including anchorage is seismically bounded by the tested or analyzed conditions.

The portions of the as-built ASME Code Design Report that apply to anchorage of the items in Table 2.3.2-1.

I 1.

Table 2.3.2-1 111Class I1E/

JILoss of ASME lTRemotely lQua]. for Sarety-M otive Code Seismic Operated Harsh Related Control Active Power Equipment Name Tag No.

Section III Cat. I Valve Envir.

Display PMS Function Position RCS Purification Motor-CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer As Is operated Isolation Valve V001 (Valve Closed l_

Position)

RCS Purification Motor-CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer As Is operated Isolation Valve V002 (Valve Closed l_

Position)

RCS Purification Motor-CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer As Is operated Isolation Valve V003 (Valve Closed Position)

CVS Resin Flush Line CVS-PL-Yes Yes No l

Containment Isolation Valve V040 CVS Resin Flush Line CVS-PL-Yes Yes No

/

l Containment Isolation Valve V041 CVS Demineralizer Resin Flush CVS-PL-Yes Yes No

/

Transfer Line Containment Isolation V042 Open/

Thermal Relief Valve Transfer Closed CVS Letdown Containment CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer Closed Isolation Valve V045 (Valve Closed l__

Position)

CVS Letdown Containment CVS-PL-Yes Yes Yes Yes/No Yes Yes Transfer Closed Isolation Valve V047 (Valve Closed l_

Position)

Table 2.3.2-1 (cont.)

Class I E/

Loss of ASME Remotely Qual. for Safety-Motive Code Seismic Operated Harsh Related Control Active Power l

Equipment Name Tag No.

Section III Cat. I Valve Envir.

Display PMS Function Position CVS Purification Return Line CVS-PL-Yes Yes No

/

Transfer Pressure Boundary Check Valve V080 Closed CVS Purification Return Line CVS-PL-Yes Yes No

- /

No Transfer Pressure Boundary Isolation V081 Closed Check Valve CVS Purification Return Line CVS-PL-Yes Yes No Transfer Pressure Boundary Check Valve V082 Closed CVS Auxiliary Pressurizer CVS-PL-Yes Yes Yes Yes/Yes No Yes Transfer Closed Spray Line Pressure Boundary V084 Closed Valve CVS Auxiliary Pressurizer CVS-PL-Yes Yes No Yes/Yes Transfer Spray Line Pressure Boundary V085 Closed Check Valve CVS Makeup Line Containment CVS-PL-Yes Yes Yes Yes/No Yes Yes Transfer As Is Isolation Motor-operated Valve V090 (Valve Closed l_

Position)

CVS Makeup Line Containment CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer As Is Isolation Motor-operated Valve V091 (Valve Closed l_

Position)

CVS Hydrogen Addition Line CVS-PL-Yes Yes Yes Yes/Yes Yes Yes Transfer Closed Containment Isolation Valve V092 (Valve Closed l_

Position)

Note: Dash (-) indicates not applicable.

Table 2.3.2-1 (cont.)

C Class I E/

Loss ofl ASME Remotely Qual. for Safety-Motive Code Seismic Operated Harsh Related Control Active Power Equipment Name Tag No.

Section 1II Cat. I Valve Envir.

Display PMS Function Position CVS Hydrogen Addition Line CVS-PL-V094 Yes Yes No Transfer l

Containment Isolation Check Closed Valve CVS Makeup Line Containment CVS-PL-V100 Yes Yes No

/

Transfer Isolation Thermal Relief Valve Open/

Transfer Closed CVS Demineralized Water CVS-PL-Yes Yes Yes Yes/No No Yes Transfer Closed Isolation Valve V136A Closed CVS Demineralized Water CVS-PL-Yes Yes Yes Yes/No No Yes Transfer Closed Isolation Valve V136B Closed Note: Dash (-) indicates not applicable.

fr.'t' a.4.

Test or Analysis

'Acceptance Criteria ITAAC Determination Basis provides makeup Testing will be performed by igning a flow path from each CVS akeup pump, actuating makeup flow i the RCS at pressure greater than or iual to 2000 psia, and measuring the ow rate in the makeup pump ischarge line with each pump suction i) Each CVS makeup pump provides a flow rate of greater than or equal to 100 gpm.

CVS preoperational acceptance test report section to makeup pump flow.

ligned

) Inspection of the boric acid tank olume will be performed.

I ii) The volume in the boric acid tank is at least 70,000 gallons between the tank outlet connection and the tank CVS preoperational acceptance test report section appi to boric acid tank volume.

Testing will be performed to asure the delivery rate from the IS to the RCS. Both CVS makeup nps will be operating and the RCS ssure will be below 6 psig.

I iii) The total CVS makeup flow to the CVS preoperational acceptance test report section RCS is less than or equal to 200 gpm. to total system makeup flow.

  • 1

HVAC (TURBINE BUILDING COMPARTMENT EXHAUST)

TGS NNS MAIN TURBINE STOP AND CONTROL VALVES MAIN STEAM-MS TGS ITO CROSSAROUND MSITGS ISTEAM TO MC-COMBINED INTERMEDIATE VALVES TO MC NNS TGS MC

- TURBINE BUILDING COMPARTMENT EXHAUST EXHAUST BLOWERS CROSSAROUND STEAM SOURCES OF GLAND SEALSTEAM 1-MAIN STEAM 0:w8 0M C,

o AS TO STEAM BYPASS VALVES STEAM SEAL HEADER ITGS TURBINE AUXILIARY STEAM In 0

0 NOTES;

1. STEAM PATH BETWEEN HIGH AND LOW PRESSURE TURBINES.
2. DELETED
3. TYPICAL FOR INTERFACES WITH MC.

Figure 2.10.9 Turbine Gland Seal System

2.a) The nuclear island structures, i) An inspection of the nuclear island including the critical sections listed in structures will be performed.

Table 3.3-7, are seismic Category I Deviations from the design due to as-and are designed and constructed to built conditions will be analyzed for withstand design basis loads as the design basis loads.

specified in the Design Description, without loss of structural integrity and the safety-related functions.

i) A report exists which reconciles deviations during construction and concludes that the as-built nuclear island structures, including the critica sections, conform to the approved design and will withstand the design basis loads specified in the Design Description without loss of structural integrity or the safety-related An inspection of the as-built acrete thickness will be performed. I ii) A report exists that concludes that the as-built concrete thicknesses conform with the building sections defined on Table 3.3-1.

A report that concludes that the as-built concrete thicknesses conform with the building sections defined on Table 3.3-1.

Table 3.3-1 Definition orWall Thicknesses for Nuclear Island Buildings and Annex Building_

l Applicable Radiation Floor Elevation or Concrete Shielding Wall Wall or Section Description Column Lines Elevation Range ThicknesPl (Yes/No)

Containment Building Internal Structure Shield Wall between Reactor Vessel Cavity and RCDT E-W wall parallel with column line 7 From 711-6' to 83'-L0 3'-0" Yes Room West Reactor Vessel Cavity Wall N-S wail parallel with column line N From 831-0' to 981'.0 7-6' Yes North Reactor Vessel Cavity Wall E-W wall parallel with column line 7 From 83'-O' to 98'-0" 97-06 Yes East Reactor Vessel Cavity Wall N-S wall parallel with column line N From 83'-0" to 98'-0' 7-6' Yes West Refueling Cavity Wall N-S wall parallel wih column line N From 98'4-" to 135.'-"

4'-0 Yes North Refueling Cavity Wall E-W wall parallel with column line 7 From 98'-0" to 1351-3" 4'

Yes East Refueling Cavity Wall N-S wall parallel with column line N From 98'-0" to 135!-3' 4'-0.

Yes South Refueling Cavity Wall E-W wall parallel with column line 7 From 98'-0" to 135 -3" 4'-O" Yes South wall of west steam generator compartment Not Applicable From 103'-0" to 135'-3' 2-6' No West wall of west steam generator compartment NotApplicable From 103'-O" to 135-3" 2-6' No North wall of west steam generator compartment/south wall Not Applicable From 103'-0" to 135t-3" and 1581-0" 2-6' Yes of pressurizer compartment West wall of pressurizer compartment Not Applicable From 107'-2" to 169'.0" 2-6" Yes North wall of pressurizer compartment Not Applicable From 107'-2" to 169'.0" 2'-6' Yes East wall of pressurizer compartment Not Applicable From 118'-6' to 169'-.0 2-6" Yes North-east wall of incontainment refueling water storage Parallel to column line N From 103'-O" to 135t-3' 2-6' No tank West wall of in-containment refueling water storage tank Not applicable From 103'-0" to 135L-3" 5/8' steel plate with No South wall of east steam generator compartment Not Applicable From 87.6" to 135-3' 21-6" Yes

1.

The column lines and floor elevations are identified and included on Figures 31through 3.3-13.

2.

These wall thicknesses have a construction tolerance of I inch, except for exterior walls below grade where the tolerance is +ih&hes,-

I inch.

3.

For walls that are part of structural modules, the concrete thickness also includes the steel face plates.

Table 3.3-1 (cont.)

Definition of Wall Thicknesses for Nuclear Island-Buildings and Annex Buildingdl)

Applicable Radiation Floor Elevation or Concrete Shielding Wall Wall or Section Descriplon Column Lines Elevation Range ThicknessP)m (Yes/No)

East wall of cast steam generator compartment Not Applicable From 94'-O" to 135-3" 2'-6" Yes North wall of east steam generator ompartment Not Applicable From 87-6" to 135'3" 2-6' Yes Shield Building Shield Building Cylinder Not Applicable From 100-O" to 265'-0' 3'-O" Yes Columns between air inlets Not Applicable From 265'-O" to 271'-6" 3-O" Yes Tension Ring Not Applicable From 27P-6" to 275'-10" 3'-

Yes Conical Roof Not Applicable From 275. IO' to 289'-O 1'-6" cast-in-place Yes concrete over 6" pro.

cast concrete ribbed conical sections PCS Tank External Cylindrical Wall Not Applicable From 298'-9" to 333'-9" 2'-T" Yes PCS Tank Internal Cylindrical Wall Not Applicable From 314'-4" to 334'-O" 1'6" Yes PCS Tank Roof Not Applicable 334'-O" V-3" No Auxiliary Building Walls/Floors Column Line I wall From Ito N From 66'-6 to 1OO'!Ol 3'-O" No Column Line I wall From I to N From IOO'-O" to I8O'-O 2-3" Yes Column Line 2 wall From I to K-2 From 66-6" to 135t'3" 2-6" Yes-Column Line 2 wall From K-2 to L-2 From 66-6" to 135'-3" 5'-0" Yes Column Line 2 wall From L12 to N From 98'-O" to 135t'3" 2-6" Yes Column Line 2 wall From I to J IFrom 135'-3 to 153'-O" 2'T" Yes Column Line 3 wall From J-1 to J32 From 66-6" to 82-6" 2'-6" Yes Column Line 3 wall From J-1 to 3-2 From I00'-O" to 135-3" 2'-6" Yes Column Line 3 wall From 1.2 to K-2 From 66-6' to 135-3' 2'-6I Yes Column Line 3 wall From K-2 to 1-2 From 66-6" to 941-3" 2-6" Yes Column Line 4 wall From I to J-From 66'-6" to 153'0" 2-6" Yes Column Line 4 wall From J-I to J-2 From 66-6" to 92'-6" 2-6" Yes Column Line 4 wall From J. lto J-2 From 100'.-" to 135'-3" 2-6" Yes

Table 3.3-1 (cont.)

Definition of Wall Thicknesses for Nuclear Island Buildings and Annex Building(')

Applicable Radiation Floor Elevation or Concrete Shielding Wall Wall or Section Descriplon Column Lines Elevation Range Thicknesf')

(Yes/No)

Column Line 4 wall From l.2 to K-2 From 66-6' to 135-3 2-6' Yes Column Line 4 wall From I to intersection with shield From 135!-3" to 1800" 2'-0 Yes building wall Column Line 5 wall From I to 3-1 From 66-6" to 1606' 2-O" Yes Column Line 7.1 wall From I to 3.1 From 66-6' to 82-6' 2-Os Yes Column Line 7.2 wall From I to 3.1 From 66-6' to I1004OO 24-O Yes Column Line 7.3 wall From I to K From 66-6' to 100t0" 3-Op Yes Column Line 7.3 wall From Ito K From 100-O0 to 160'-6 2..O' No Column Line II wall From Ito Q From 66-6' to I 00-O 3'-0 No Column Line II wall From I toQ From 100lOO to 117.-6' 2.-O Yes Column Line II wall From I to L From 117-6' to 153.O' 2'-0 Yes Column Line II wall From L to M From I 17-6 to 13 5-3 44-Yes Column Line II wall From M to P From I 17 -6' to 135-3' 2'-0 Yes Column Line II wwl From P to Q From II 7-6' to 135L3 4'-4 Yes Column Line 11 wall From L to Q From 135-3L to 153 4 O

2 Yes Column Line I wall From I to II From 66-6' to IO000" 3-Os No Column Line I wall From I to 4 From 100-O to 808-O.

2-O0 Yes Column Line I wall From 4 to 7.3 From 1004-to 160-6 2-O" No Column Line I wall From 7.3 to I I From 1004-O to 1534O 2 -O" No Column Line 3.1 wall From I to 2 From 82-6' to 100'-O 2'-O Yes Column Line J.1 wall From 2 to 4 From 66-6' to 135-3 2-6 Yes Column Line 3.1 wall From 2 to 4 From 135-3' to 1534.O' 2-Os Yes Column Line 3.1 wall From 4 to 5 From 66-6' to 107-2' 24-Yes Column Line 3.2 wall From 2 to 4 From 66-6 to 135-3' 2-6' Yes Column Line 3.2 wall From 4 to intersection witkhield From 82'-6' to 107-21 2'-0 Yes building wall Column Line K-2 ivall From 2 to 4.

From 66-6' to 13 5-3 4-9' Yes Column Line 1,2 wall From 2 to 4 From 66'-6 to 135-3' 4 -4 Yes Column Line N wall From I to 2 From 66-6" to 119L9" 3'-tY No

Table 3.3-1 (cont.)

Definition of Wall Thicknesses for Nuclear Island Buildings and Annex Building(X)

Applicable Radiation Floor Elevation or Concrete Shielding Wall Wall or Section Descripion Column Lines Elevation Range Thicknessf' (Yes/N o)

Column Line N wall From I to 2 From 119'9" to 135-3" 3'-O Yes Column Line N wall From 2 to 4 From 66-6" to 98'-O" 3'-O" No Column Line N wall From 2 to 4 From 9S'-0" to 135'-3" 5'-6" Yes Column LineNwall From I to4 From 135'-3" to 180'-O" 2'-O" Yes Column Line J wall From 7.3 to II From 66-6" to II 7-6" 2'-0 No Column Line K wall From 7.3 to II From 60'-6" to 135:3" 2'-O Yes Column Line L wall From shield building wall to II From 60'-6' to 153'-0 2'-O Yes Column Line M wall From shield building wall to 11 From 66-6 to 153'-0" 2'-O0 Yes Column Line P wall From shield building wall to 11 From 66-6" to 153'-O" 2'-O0 Yes Column Line Q wall From shield building wall to II From 66-6" to I00'-0 3'-O" No Column Line Q wall From shield buildhg wall to II From I00'-O to 153'-O" 2'-O" Yes Labyrinth Wall between Col. Line 3 and 4 and-J to J-2 Not Applicable From 82-6' to 100'-O4 2'-O" Yes N-S Shield Wall (low wall)

Between K-2 and L-2 extending from From 100'-0" to 107'-2 2-6' Yes column line I north N-S Shield Wall Between K-2 and L-2 extending from From 100'-O" to 125'-O" 2-3' Yes column line I north E-W Shield Wall Between I and 2 extending from From 100'-O" to 125'-0" 2-9" Yes column line N east Column Line 9.2 wall From I to J ad K to L From 117'-6 to 135:3" 2'-O0 Yes Labyrinth Wall between Column Line 7.3 and 9.2 and J to K Comer wall From 117-6" to 135-3" 2'-O0 Yes Auxiliary Area Basemat From -1 I and I-Q, excluding shield From 60'-61 to 66'-6" 6'-O" No building Nuclear Island Basemat Below shield building From 60'-6" to containment vessel 6'-O" to 22'-0" (varies)

No or 82'-6" Floor From I to 2 and I to N 82-6' 2'-O" Yes Floor From 2 to 5 and i-I to J-2 82-6" 0'-9" Yes Pipe Chase Floor From 2 to 5 and J.1 to J-2 92'-6" 2'-0" Yes Floor From 2 to 3 and 3-2 to K-2 90'-3" 3'-0" Yes Floor From 3 to 4 and 3-2 to K-2 92-6" 2'-0" Yes Floor From 4 to 7.3 and I to JI 82'-6' 2'-0" Yes

Table 3.3-1 (cont.)

Definition of Wall Thicknesses for Nuclear Island Buildings and Annex Building(X)

Applicable Radiation Floor Elevation or Concrete Shielding Wall Wall or Section Descripfon Column Lines Elevation Range ThicknesP'2 (Yes/No)

Floor From I to 2 and I to N 100,-a" 3'-0w Yes Floor From 2 to 4 and K-2 to 1,2 92'-8" 3'

Yes Floor From I to 3.2 and 4 to intersecting 107'-2' 2'-O" Yes vertical wall before column line 5 Floor From I to shield building wall and 107'-2" O-9" Yes from intersecting vertical wall before column line 5 to column line 5 Floor From 5 to 7.3 and I to shield building 100'-0 2TV Yes wall Floor From K to L and shield building wall I00'.O" 0(-9" Yes to column line 10 IO Floor From I to 1.6 and 1,2 to N 125'-O" 3'-4Y Yes Floor From 1.6 to 2 and t,2 to N 17'-6 2'-0" Yes Main Control Room Floor From 9.2 to II and I to L II T-6 2-0" Yes Floor Bounded by shield bldg, 7.3, J. 9.2 11 7-6" 2'-0T Yes and L Floor From 9.2 to II and L to Q 117'-6 2-0 Yes Floor From 3 to 4 and J2 to K-2 I I T-6 2'-0 Yes Floor From 2 to 4 and I to l1 153'-O"

-.3' Yes Floor From I to 4 and Ito N 180O w13" Yes Floor From 4 to short of column line 5 and 1355'-

0'-9" Yes from I to intersection with shield l_

building wall Floor From short of column line 5 to 133'-0" OL-9 Yes column line 5 and from I to intersection with shield building wall Floor From 5 to7.3 and from I to 135'-3' 0'-9" Yes intersection with shield building wall I Annex Building Column line 2 wall l From E to H From 107-2" to 135-3"l 19 3/4" Yes Column line 4 wall From E to H From 107.2" to l62-6 & 166'-0" l

2T" Yes N-S Shield Wall beiveen E and F From 2 to 4 From IO7-2" to 135-3' 1-0"l Yes

Table 3.3-1 (cont.)

Definition of Wall Thicknesses for Nuclear Island Buildings and Annex BuildingM' Applicable Radiation Floor Elevation or Concrete Shielding Wall Wall or Section Descripf on Column Lines Elevation Range Thicknessfx3)

(Yes/ No)

Column line 4.1 wall From E to H From 107-2" to 135'-3 2-0w Yes E-W Labyrinth Wall between column Not Applicable From 100-0" to 112-0 2-0" line 7.1 and7.8 and G to H N-S Labyrinth Wallbetween column Not Applicable From 100'-0" to 112V0" 2 -0" line 7.8 and9 and G to If E-W Labyrinth Wall between column Not Applicable From 1004-to 112-0" 2-0" Yes line 7.1 and 7.8 and G to H N-S Labyrinth Wall between column Not Applicable From 100'O4 to 112-O 2.0 Yes line 7.8 and9 and G to H N-S Shield Wall on Column line. F From 4.1 North From 100 -0" to I 7T-6" 1'

Yes Column Line 9 wall From E to connecting wall From 107-2" to II T76' 2 -O Yes between G and H Column Line E wal From 9 to 13 From 100-0 to 135-3" 2'-0 Yes Column Line 13 wall From E to 1.1 From 100'-0" to 135-3" 2-0" Yes Column Line 1.1 wall From 11.09 to 13 From 100-0" to 135!-3" 2-0 Yes Corridor Wall between 0 and H From 9 to 13 From 100-0" to 135-3' I-6' Yes Column Line 9 wall From Ito H From I 17'6" to 15S'-0" 24-0 Yes Floor 2 to 4 from shield wall between E 135-3 0'-6 Yes and F to column line H Floor From 4 to 4.1 and E to If 135-3" 1:-0 Yes Floor From 9 to 13 and Eto 1.1 117'-6 0'-6 Yes Floor From 9 to 13 and Eto 1.1 135-3' 0-S" Yes Containment Filtration RmA (North Wall)

Between column lineE to Hf From 135L3' to 158-0 I -0" Yes Containment Filtration RmA (East wall)

Between column line E to F From 135-3' to 158-0" 11-0" Yes Containment Filtration RmA (West wall)

Between column line Gto H From 135-3" to 158W-0" 1-01 Yes Containment Filtration RmnA (Floor)

Between column ine Eto H 135-3' I'-0_

Yes Containment Filtration RmB (Floor)

Between column line Eto H 146-3' 0-6 Yes Containment Filtration RmB (West wall)

Between column line Gto H From 146-3" to I580" P-0" Yes North wall (Room 50351)

N/A 100-0" to top of wall 1 4" Yes East Wall (Room 50351)

DR from 2R past 3R1 00'-0" to top of wall I-4 Yes

Table 3.3-1 (cont.)

Definition of Wall Thicknesses for Nuclear Island Buildings and Annex Building()

Applicable Radiation Floor Elevation or Concrete Shielding Wvall Wall or Section Descripfon Column Lines Elevation Range Thickness'm (Yes/No)

West wall (Room 50351)

DR from 2R past 3R 100'-0Y to top of wall 11-4 Yes East wall (Room 50352)

FR from IR to 2R1 I 00-0 to top of wall 2 -O0 Yes South wall (Room 50352)

IR from FR to DR 100-0" to top of wall 2-0" Yes West Wall (Room 50352)

DR from IR to 2R1 00'-O" to top of wall 2.-O0 Yes

Table 3.3-7 Nuclear Island Critical Structural Sections Containment Internal Structures South west wall of the refueling cavity South wall of the west steam generator cavity North east wall of the in-containment refueling water storage tank In-containment refueling water storage tank steel wall Column supporting the operating floor Auxiliary and Shield Building South wall of auxiliary building (column line 1), elevation 66!6" to elevation 180'-O" Interior wall of auxiliary building (column line 7.3), elevation 66!6" to elevation 160'-6" West wall of main control room in auxiliary building (column line L), elevation 117'-6" to elevation 153'-O" North wall of MSIV east compartment (column line 11 between lines P and Q), elevation 117'-6" to elevation 153'-O" Shield building cylinder, elevation 160'-6" to elevation 200"-O" Roof slab at elevation I 80'-O" adjacent to shield building cylinder Floor slab on metal decking at elevation 135-3" 2'-O" slab in auxiliary building (tagging room ceiling) at elevation 13513" Finned floor in the main control room at elevation 135L3" Shield building roof, exterior wall of the PCS water storage tank Shield building roof, tension ring and columns between air inlets, elevation 265'-O" to elevation 275'-10" Divider wall between the spent fuel pool and the fuel transfer canal Nuclear Island Basemat Below Auxiliary Building Bay between reference column lines 9.1 and 11, and K and L Bay between reference column lines I and 2 and K-2 and N

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