ML071580360

Calculation H21C-093, Rev 00, LOCA Bypass Piping Models for Alternative Source Term Methodology (Ast).

ML071580360
Person / Time
Site:	Nine Mile Point
Issue date:	07/30/2004
From:	Gardner S, Stinson G Nuclear Engineering Co
To:	Office of Nuclear Reactor Regulation
References
H21C-093, Rev 00
Download: ML071580360 (70)

Text

Nine Mile Point Unit 2 Alternative Source Term Calculation H21C-093 "LOCA Bypass Piping Models for Alternative Source Term Methodology (AST)"

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Discipline:

Total Tot ast 69 ANALYSIS 69 Ii writle .Calculation No.

LOCA Bypass Piping Models for Alternative Source H21C-093 Term Methodology (AST) (Sub)system(s) Building Floor Elev. Index No..

N/A N/A N/A N/A Originator(s)

Shane R. Gardner (CNS)

Reviewer(s) I Approver(s)

-Glenn Stinson I

Eval., DER, or Prep'd Reviewed Rev Description Change No. Date By Date A Date 00 ORIGINAL ISSUE N/A 0510'Y10 -1/ýO/r _A.L Computer Output/lMicrofilm Filed Separately (Yes I No I NA): Yes Safety Class (SR NSR I Qxx): SR Superseded Document(s): NONE

,Document Cross Reference(s) - For additional references see page(s): 63 -0AL Ref Doc No Document No. Type Index Sheet Rev General Reference(s) :.See pages 63 r06 . L '/-s/O(

Remarks :

The purpose of this calculation is to document the physical characteristics associated with primary containment piping which may serve as bypass leakage pathways during a design basis Loss of Coolant Accident (LOCA) in NMP Unit 2. This calculation documents piping lengths, internal areas, volumes, and degrees of bend that are appropriate for use in fission product deposition removal methodologies associated with Alternative Source Term (AST) guidance set forth in R. G. 1.183 and implemented in the RADTRAD computer code and/or other applicable deposition models.

Confirmation Reurd(e o:N Final Issue Status: Turnover See Page(s) : NONE IAPP IRequired ( Yes INIA) :N/A 10CFR50.59 Evaluation Number(s): N/A Component ID(s) (As shown in MEL):

Copy of Applicability Determination or 50.59 Screen NIA Attached? Yes C3 No El.

Key Words : Alternative Source Term, AST, Regulatory

&uide 1.183, Control Room Habitability, CRH, LOCA pass Leakage, Brockmann Bixler, Fission Product

• emoval

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Project.Nine Mile Point NuclearStation Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00

-ef.

Table of Contents

1. O bjective ....................................................................................................................................... 6

2. Background ........................................................................................ I.......................................... 6

3. Method ............................................................. 6

4. Data/Assum ptions .......................................................................................................................... 8 4.1. Main Steam Lines (MSL) ........................................................................................................ 8 4.2. Main Steam Drain Lines ...................................................................................................... 17 4.3. Drywell Drains ........................................................................................................................... 18 4.4. Feedwater Lines ...................................................................................................................... 21 4.5. Primary Containment Purge (CPS) Lines in Drywell/Wetwell .............................................. 24 4.6. Reactor W ater Cleanup (RW CU) Line ................................................................................. 27 4.7. Post Accident Sam pling System (PASS) Lines .................................................................. 27 4.8. Instrum ent Air (OAS) Lines .................................................................................... ..................... 32 4.9. Nitrogen System (G SN) Line .............................................................................................. 36 4.10. 1" Prim ary Containm ent Purge (CPS) Lines ....................................................... 37 4.11. Pipe Data for Bypass Lines Evaluated .................................... 38

5. Calculations .................................................................................................................................. 40

6. Results ......................................................................................................................................... 49 6.1. Main Steam Lines (MSL) ................................................................................ 49 6.2. Main Steam Drain Lines ..................................................................................................... 50 6.3. Drywell Drains ............................................................................................................................ 51 6.4. Feedwater Lines ........................................................................................................... I.......... 52 6.5. Primary Containment Purce (CPS) Lines in Drywell/Wetwell .............................................. 53 6.6. Reactor W ater Cleanup (RW CU) Line ................................................................................. 54 6.7. Post Accident Sam pling System (PASS) Lines ....................................... ................................. 54 6.8. Instrum ent Air (OAS) Lines ................................................................................................... 56 6.9. Nitrogen System (G SN) Line ............................................................................................... 57 6.10. 1" Prim ary Containm ent Purge (CPS) Lines ..................................................................... 58 6.11. Sum mary of Results ........................................................................................................... 59

7. Conclusions .................................................................................................................................. 62

8. References .............................................................................................................................. I...... 63

9. Appendices .................................................................................................................................... 69 D:\Calc File\H21 C-093 Rev 000.doc

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Project: Nine Mile Point Nuclear Station Unit: 2- Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 ief.

List of Tables Table 3-1 Deposition/Holdup Criteria for Bypass Lines ................................................................................... 7

-r CL kti ti A I1 I i

,..Q# I in-~ A Ink i l A, Di. r1 e D . .............................................................. .............................

a Table 4.1-2 Main Steam Line A Interstitial Pipe Data ........................................................................................ 9 Table 4.1-3 Main Steam Line A Outboard Pipe Data ......................................................................................... 10 Table 4.1-4 Main Steam Line B Inboard Pipe Data ..................................................................................... 10 Table 4.1-5 Main Steam Line B Interstitial Pipe Data ...................................................................................... 12 Table 4.1-6 Main Steam Line B Outboard Pipe Data ........................................................................................ 12 Table 4.1-7 Main Steam Line C Inboard Pipe Data ..................................................................................... 13 Table 4.1-8 Main Steam Line C Interstitial Pipe Data ................................................................................... 14 Table 4.1-9 Main Steam Line C Outboard Pipe Data........................................................................................ 14 Table 4.1-10 Main Steam Line C Inboard Pipe Data .................................................................................. 15 Table 4.1-11 Main Steam Line D Interstitial Pipe Data .................................................................................... 16 Table 4.1-12 Main Steam Line D Outboard Pipe Data ..................................... ..................................... 16 Table 4.2-1 Inboard Main Steam Line Drain Inboard Pipe Data .................................................................. 17 Table 4.2-2 Inboard Main Steam Line Drain Interstitial Pipe Data ................................................................... 17 Table 4.2-3 Outboard Main Steam Line Drain Inboard Pine Data .............................. 18 Table 4.3-1 Drywell Floor Drain Inboard Pipe Data ..................................................................................... 18 Table 4.3-2 Drywell Floor Drain Interstitial Pipe Data ................................... ...................................... 19 Table 4.3-3 Drvwell Floor Drain Tank Vent Interstitial Pipe Data .................................................... 19 Table 4.3-4 Drywell Equipment Drain Inboard Pipe Data ............................................... 20 Table 4.3-5 Drywell Equipment Drain Interstitial Pipe Data ............................................................................ 20 Table 4.3-6 Drywell Equipment Drain Tank Vent Inboard Pipe Data .............................................................. 20 Table 4.3-7 Drywell Equipment Drain Tank Vent Interstitial Pipe Data ............................................................ 20 Table 4.4-1 Feedwater Line A Inboard Pipe Data ........................................................................................... 21 Table 4.4-2 Feedwater Line A Interstitial Pipe Data ......................................................................................... 22 Table 4.4-3 Feedwater Line A Outboard Pipe Data ........................................................................................ 22 Table 4.4-4 Feedwater Line B Inboard Pipe Data ........................................................................................... 22 Table 4.4-5 Feedwater Line B Interstitial Pipe Data ......................................................................................... 23 Table 4.4-6 Feedwater Line B Outboard Pipe Data ........................................................................................ 23 Table 4.5-1 2" CPS Line in Drywell Inboard Pipe Data ............................................... ......................................... 24 Table 4.5-2 2" CPS Line in Drywell Interstitial Pipe Data ........................................................................... 24 Table 4.5-3 14" CPS Line in Drywell Inboard Pipe Data ................................................................................. 25 Table 4.5-4 14" CPS Line in Drywell Interstitial Pipe Data ............................................................................... 25 Table 4.5-5 12" CPS Line in Wetwell Inboard Pipe Data ................................................................................. 25 Table 4.5-6 12" CPS Line in Wetwell Interstitial Pipe Data ............................................................................ 26 Table 4.5-7 2" CPS Line in Wetwell Inboard Pipe Data ................................................................................. 26 Table 4.5-8 2" CPS Line in Wetwell Interstitial Pipe Data ............................................................................... 26 Table 4.6-1 RWCU Line Inboard Pipe Data .............. .............................. 27 Table 4.6-2 RWCU Line Interstitial Pipe Data ................................................................................................ 27 Table 4.7-1 PASS Sample Line A Inboard Pipe Data ...................................................................................... 27 Table 4.7-2 PASS Sample Line A Interstitial Pipe Data ....................................................................................... 28 Table 4.7-3 PASS Sample Line B Inboard Pipe Data ...................................................................................... 28 Table 4.7-4 PASS Sample Line B Interstitial Pipe Data ................. ............................................................... 30 Table 4.7-5 PASS Return Line A Inboard Pipe Data ..................................................................................... 30 Table 4.7-6 PASS Return Line A Interstitial Pipe Data ................................................................................... 31 Table 4.7-7 PASS Return Line B Inboard Pipe Data. ...................................... 31 Table 4.7-8 PASS Return Line B Interstitial Pipe Data ..................................... 32 Table 4.8-1 lAS Line 1 Inboard Pipe Data ....................................................................................................... 32 Table 4.8-2 lAS Line 1 Interstitial Pipe Data .................................................................................................. 33 P:\Calc File\H21 C-093 Rev 000.doc

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Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 0 ieT.

Table 4.8-3 lAS Line 2 Inboard Pipe Data ............................................................................................................. 33 Table 4.8-4 lAS Line 2 Interstitial Pipe Data ................................................................................................... 34 Table 4.8-5 lAS Line 3 Inboard Pipe Data ....................................................................................................... 34 Table 4.8-6 IAS Line 3 Interstitial Pipe Data .................................................................................................... 34 Table 4.8-7 lAS Line 4 Inboard Pipe Data ....................................................................................................... 35 Table 4.8-8 IAS Line 4 Interstitial Pipe Data .................................................................................................... 35 Table 4.8-9 lAS Line 5 Inboard Pipe Data ........................................................................................................... 36 Table 4.8-10 lAS Line 5 Interstitial Pipe Data ................................................................................................. 36 Table 4.9-1 GSN Line Interstitial Pipe Data ............................................ 36 Table 4.10-1 1" CPS Line I Interstitial Pipe Data ........................................ 37 Table 4.10-2 1" CPS Line 2 Interstitial Pipe Data ........................................................................................... 37 Table 4.11-1 Bypass Line Q A Classification and Size Data Sum m ary .................................... ........................... 38 Table 6.1-1 Main Steam Line A Results ......................................................................................................... 49 Table 6.1-2 Main Steam Line B Results ......................................................................................................... 49 Table 6.1-3 Main Steam Line C Results ......................................................................................................... 49 Table 6.1-4 Main Steam Line D Results ......................................................................................................... 50 Table 6.2-1 Inboard Main Steam Line Drain Results ..................................................................................... 50 Table 6.2-2 O utboard Main Steam Line Drain Inboard Results ..................................................................... 50 Table 6.3-1 Drywell Floor Drain Results ...................................................................................................... 51 Table 6.3-2 Drywell Floor Drain Tank Vent Results ........................................................................................ 51 Table 6.3-3 Drywell Equipm ent Drain Results .................................................................................................. 51 Table 6.3-4 Drywell Equipm ent Drain Tank Vent Results .............................................................................. 52 Table 6.4-1 Feedwater Line A Results ........................................................................................................... 52 Table 6.4-2 Feedwater Line B Results ........................................................................................................... 52 Table 6.5-1 2" CPS Line in Drywell Results .................................................................................................... 53 Table 6.5-2 14" CPS Line in Dryw ell Results ................................................................................................. 53 Table 6.5-3 12" CPS Line in W etwell Results ................................................................................................. 53 Table 6.5-4 2" CPS Line in W etwell Results ................................................................................................... 54 Table 6.6-1 RW CU Line Results .......................................................................................................................... 54 Table 6.7-1 PASS Sam ple Line A Results ...................................................................................................... 54 Table 6.7-2 PASS Sam ple Line B Results ..................................................................................................... 55 Table 6.7-3 PASS Return Line A Results ......................................................................................................... 55 Table 6.7-4 PASS Return Line B Results ......................................................................................................... 55 Table 6.8-1 IAS Line 1 Results .............................................................................................................................. 56 Table 6.8-2 IAS Line 2 Results .............................................................................................................................. 56 Table 6.8-3 lAS Line 3 Results .................................................................................................. .......................... 56 Table 6.8-4 AS Line 4 Results .................................................................................... ........................................ 57 Table 6.8-5 IAS Line 5 Results ................................................................... 57 Table 6.9-1 GSN Line Results ............................................................... ............................................................. 57 Table 6.10-1 1" C PS Line 1 Results ..................................................................................................................... 58 Table 6.10-2 1" CPS Line 2 Results .............................................................................................. 58 Table 6.11-1 Sum m ary of Pipe Data: Bends and Lencith .................... ..... ..... .......... .................... 59 Table 6.11-2 Sum m ary of Results: Internal Areas .......................................................................................... 60 Table 6.11-3: Summ ary of Results: Internal Volum es .................................................................................... 61 S

D:\Calc FilekH-121C-093 Rev OOO.doc

NUCLEAR ENGINEERIN AC LTO OTNAIN SEE IPage 5Io 0 Project:Nine Mile Point Nuclear Station Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 Ref, List of Figures Figure 5-1 Schematic of Main Steam Line and Main Steam Drain Line Bypass ..................... 41 Fiqure 5-2 Schematic of Drywell Equipment Drain and Vent Bybass ............................................................. 42 Figure 5-3 Schematic of Drywell Floor Drain and Vent Bypass .................................................................... 43 Figure 5-4 Schematic of Feedwater Bypass ................................................................................................... 44 Figure 5-5 Schematic of 2". 12" and 14" CPS Bypass .................................................................................. 45 Figure 5-6 Schem atic of RW CU Bypass ........................................................................................................ 46 Figure 5-7 Schematic of PASS Bypass ........................................................................................................... 47 Finlir R-R Schematic of Combined IA*/(*N,*/C~PR Bv ........................................ 4R Figure 9-1 Directory Listing of Excel Spreadsheets ............................................................................................. 69 0

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1. Objective The purpose of this calculation is to document the physical characteristics associated with primary containment piping which may serve as bypass leakage pathways during a design basis Loss of Coolant Accident (LOCA) in NMP Unit 2. This calculation documents piping lengths, internal areas, volumes, and degrees of bend that are appropriate for use in fission product deposition removal methodologies associated with Alternative Source Term (AST) guidance set forth in Regulatory Guide 1.183 (Reference 8.1) and implemented in the RADTRAD (Reference 8.7) computer code.

Additionally, the results developed herein may be used for the analysis of fission product deposition in main steam lines according to the methodology provided in NRC SER AEB-98-03 (Reference 8.2).

2. Background

0 Guidance for modeling the removal of radioactive fission products due to various physical mechanisms is provided in the Alternative Source Term methodology per RG 1.183. The following guidance from RG 1.183 Appendix A, as directed by Regulatory Positions 1.2.1 and 1.3.2, provide acceptable criteria regarding the deposition credit for fission product removal in bypass leakage.

4.5. Primary containment leakage that bypasses the secondary containment should be evaluated at the bypass leak rate incorporated in the technical specifications. If the bypass leakage is through water, e.g., via a filled piping run that is maintained full, credit for the retention of iodine and aerosols may be considered on a case-by-case basis. Similarly, deposition of aerosol radioactivity in gas-filled lines may be considered on a case-by-case basis.

6.3. Reduction of the amount of released radioactivity by deposition and plateout on steam system piping upstream of the outboard MSIVs may be credited, but the amount of reduction in concentration allowed will be evaluated on an individual case basis. Generally, the model should be based on the assumption of well-mixed volumes, but other models such as slug flow may be used ifjustified.

6.5 A reduction in MSIV releases that is due to holdup and deposition in main steam piping downstream of the MSIVs and in the main condenser, including the treatment of air ejector effluent by off gas systems, may be credited if the components and piping systems used in the release path are capable of performing their safety function during and following a safe shutdown earthquake (SSE). The amount of reduction allowed will be evaluated on an individual case basis.

3. Method 0

The piping which comprises the current Nine Mile Point Unit 2 (NMP2) LOCA bypass releases (References 8.3 through 8.6) and which includes main steam isolation valve (MSIV) leakage is reviewed to determine the following design information: horizontal and vertical lengths and total degrees of bends. Reference piping specifications and drawings are then used in conjunction with the gathered design information to calculate the internal volume and deposition areas. The portion of each line that is acceptable for deposition'credit is determined using guidance set forth in RG 1.183 (Reference 8.1).

D:\Calc Flle\H2lC-093 Rev 000.doc

tNUCLEARENGINEERI CALCULATION CONTINUAT IPage 7o 0 Project:Nine Mile PointNuclear Station Originator/Date I Reviewer/Date Unit:

Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 15T.

Table 3-1 provides a matrix of criteria utilized in determining which line portions are credited for bypass holdup and deposition. A more detailed explanation of the table and the assumptions taken are provided in the Section 4 Data/Assumptions.

Table 3-1 Deposition/Holdup Criteria for Bypass Lines Criteria MSIV Other All piping Seismic Category I and QA X X CAT 1 Deposition credit for piping upstream of inboard isolation valvel]

Holdup credit for piping upstream of inboard isolation valve Deposition credit 1 for piping between _

X _

X isolation valves Holdup credit for piping between isolation valveslI' Deposition credit for piping downstream X of outboard isolation valve 12]

Holdup credit for piping downstream of 12 outboard isolation valve ) _

[1] In accordance with Section 6.3 of R. G. 1.183 Appendix A, credit for deposition in main steam piping upstream of the outboard MSIV may be taken and is implemented for appropriate line (unfailed) conditions. Credit for iodine deposition not taken for portions of lines which are assumed to be failed or assumed open to the atmosphere.. The majority of the main steam horizontal piping is from the reactor to the inboard MSIV.

[2] The majority of non-MSIV bypass lines do not have Seismic Category I/QA CAT 1 piping beyond the outboard isolation valve. Therefore, this piping is conservatively neglected.

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NUCLEAR ENGINEERING CALCULATI ONTINUATION SHEET Page 8 (Next Project:Nine Mile PointNuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 Het.

4. Data/Assumptions RG 1.183 provides positions in regards to holdup and pipe deposition for MSIV and primary containment bypass leakage lines as delinea.ted above in Sections 2 & 3. In light of the positions set forth in RG 1.183, the following assumptions are taken regarding the portion of piping acceptable for credit.

Assumption (1) - In accordance with RG 1.183, credit for deposition in main steam piping upstream of the outboard MSIV may be taken and is implemented. The majority of the main steam horizontal piping is from the reactor to the inboard MSIV. Deposition credit is applied to horizontal piping only.

Assumption (2) - Transport time or 'holdup' is a physical characteristic of any flow process. Credit for decay of radionuclides during the flow process is taken. This is referred to as 'holdup'. Holdup credit for piping volumes is taken and is applied to total (horizontal plus vertical) piping volume for unfailed lines. Holdup is not credited for portions of lines which are assumed to be failed.

In the tables below, the raw data extracted from plant piping diagrams as referenced in Section 8 is shown.

4.1. Main Steam Lines (MSL)

Table 4.1-1 Main Steam Line A Inboard PiDe Data MSL "A" Piping Leading Up To Inboard IV Starting Location: Reactor Stopping Location: MSIV 2MSS*AOV6A Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-026-43-1 8.11, 8.12, 8.19 2 9 1/4  :

2-MSS-026-43-1 8.11, 8.12, 8.19 90 3 3 i  :

2-MSS-026-43-1 8.11, 8.12, 8.19,_ 3 3 2-MSS-026-43-1 8.11,8.12, 8.19__ 3 11 2-MSS-026-43-1 8.11,8.12, 8.19 _ 3 3 3/4 2-MSS-026-43-1 8.11,8.12,8.19  : 2 11 2-MSS-026-43-1 8.11,8.12, 8.19 i 1 2 j1/4 2-MSS-026-43-1 8.11, 8.12,8.19 _ _10 4 3/4 2-MSS-026-43-1 8.11, 8.12, 8.19 90 i 3 3 2-MSS-026-43-1 8.11,8.12, 8.19 3 3 :i i 2-MSS-026-43-1 8.11, 8.12, 8.19 6 4 3/4 _

2-MSS-026-43-1 1 8.11, 8.12,8.19 11 :_ _

2-MSS-026-43-1 8.11, 8.12, 8.19 1 1 3/8 i 2-MSS-026-43-1 8.11, 8.12, 8.19 2 10  :  :

2-MSS-026-43-1 8.11, 8.12, 8.19 1 3 3/4 _

2-MSS-026-43-1 8.11, 8.12, 8.19 11 3/4 D:\Calc File\H21 C-093 Rev OO0.doc

INUCLEAR ENGINEERING. CALCULATIO CONTINUA SHEET IPage--9 0 Project:Nine Mile PointNuclear Station Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 517/04 Glenn Stinson / 7/30/04 H21 C-093 00 He?.

MSL "A" Piping Leading Up To Inboard IV Starting Location: Reactor Stopping Location: MSIV 2MSS*AOV6A Bends Horizontal Length Vertical Length 2-MSS-026-43-1 8.11, 8.12, 8.19 6 1/4 -

2-MSS-026-43-1 8.11, 8.12, 8.19 2 10 ' ',

2-MSS-026-43-1 8.11, 8.12, 8.19 1 3 7/8 - i 2-MSS-026-43-1 8.11, 8.12, 8.19 90 3 3 " "

2-MSS-026-43-1 8.11, 8.12, 8.19 ', 3 3 2-MSS-026-43-1 8.11, 8.12, 8.19  : 9 1/4 2-MSS-026-43-1 8.11, 8.12, 8.19 10 1/4 2-MSS-026-43-1 8.11, 8.12, 8.19  ; 7 2 1/8 2-MSS-026-43-1 8.11,8.12,8.19 11 3/4 2-MSS-026-43-1 8.11, 8.12, 8.19 '1 10 1/2 2-MSS-026-43-1 8.11, 8.12, 8.19 __1_10_9 1/8 2-MSS-026-43-1 8.11, 8.12, 8.19 1921 3/4 2-MSS-026-43-1 8.11, 8.12,8.19 _ 21 3 3/8 2-MSS-026-43-1 8.11, 8.12,8.19 90 _3 3 2-MSS-026-43-1 8.11, 8.12, 8.19 3 3 __3/ 1 2-MSS-026-43-1 8.11, 8.12, 8.19 1 2 3/4 2-MSS-026-43-1 8.11,8.12, 8.19 3 8 1/4 ,,

2-MSS-026-43-1 8.11,8.12,8.19 11 1/8  ;

1. Gradual bend (-21 deg.) neglected.

Table 4.1-2 Main Steam Line A Interstitial Pipe Data MSL "A" Interstitial Piping Between IVs Starting Location: MSIV 2MSS*AOV6A Stopping Location: MSIV 2MSS*AOV7A Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-026-152-1 8.12, 8.20, 8.28 1 6 1/2 _

2-MSS-026-152-1 8.12, 8.20, 8.28 13 3 1/4 -

2-MSS-026-152-1 8.12, 8.20,8.28 3 11 1/4 '

2-MSS-026-152-1 8.12, 8.20,8.28 1 i _

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• 0 Project:Nine Mile Point Nuclear Station Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H211C093 00

ef, Table 4.1-3 Main Steam Line A Outboard Pipe Data MSL "A" Piping After Outboard IV

-Starting Location: MSIV 2MSS*AOV7A Stopping Location: 4' 0" before 2MSS-MSV1A Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-028-1-4 8.28, 8.21 90 32 8 ___

2-MSS-028-1-4 8.28, 8.31  ; 3 6 _

2-MSS-028-1-4 8.28, 8.31 ', 3 11 '

2-MSS-028-1-4 8.28, 8.31 i 4 5 1/2 2-MSS-028-1-4 8.28, 8.31 _ 1 1 5/8 2-MSS-028-1-4 8.28, 8.31 _ 14 8 2-MSS-028-1-4 8.28, 8.31 "_8 6 5/8 2-MSS-028-1-4 8.28, 8.31  ; 11 1/2 2-MSS-028-1-4 8.28, 8.31 __ 4 6 1/2 2-MSS-028-1-4 8.28, 8.31 90 _ 3 6 2-MSS-028-1-4 8.28, 8.31 3 6 " _

2-MSS-028-1-4 8.28, 8.31 2 1 ', 7/8 _,

0 2-MSS-028-1-4 2-MSS-028-1-4 2 8.28, 8.31 8.28, 8.31 9

2 2

2 1/8 2-MSS-028-2-4 2 8.30, 8.32 28 6 i i

2. Includes length through 48" main steam header.

Table 4.1-4 Main Steam Line B Inboard Pipe Data MSL "B" Piping Leading Up To Inboard IV Starting Location: Reactor Stopping Location: MSIV 2MSS*AOV6B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-026-44-1 8.13, 8.14, 8.19 2 9 :9/16 _

2-MSS-026-44-1 8.13, 8.14, 8.19 90 3 3 i i 2-MSS-026-44-1 8.13, 8.14, 8.19 _ 3 3 2-MSS-026-44-1 8.13, 8.14, 8.19,T 7 4 1/8 2-MSS-026-44-1 8.13, 8.14, 8.19,: 4 2  : 3/8 2-MSS-026-44-1 8.13, 8.14, 8.19 _ 1 0 1/2 2-MSS-026-44-1 8.13, 8.14, 8.19,_ 3 11 7/8 2-MSS-026-44-1 8.13, 8.14, 8.19 i 2 4  : 3/8 2-MSS-026-44-1 8.13, 8.14, 8.19 45 _ 1 4 3/16 2-MSS-026-44-1 8.13, 8.14, 8.19 _ 1 4 3/16 2-MSS-026-44-1 8.13, 8.14, 8.19 r 1 10 i 2-MSS-026-44-1 8.13, 8.14, 8.19 90 3 3 D:\CaIc File\H21C-093 Rev O00.doc

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Project:Nine Mile Point NuclearStation Unit: 22 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 Het.

MSL "B" Piping Leading Up To Inboard IV Starting Location: Reactor Stopping Location: MSIV 2MSS*AOV6B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet inches 2-MSS-026-44-1 8.13, 8.14, 8.19 3 3  : i 2-MSS-026-44-1 8.13, 8.14, 8.19 1 11 1/2 _

2-MSS-026-44-1 8.13, 8.14, 8.19 2 8 7/8 _

2-MSS-026-44-1 8.13, 8.14, 8.19 1 8 _ ',

2-MSS-026-44-1 8.13, 8.14, 8.19 8 3/8 _

2-MSS-026-44-1 8.13, 8.14, 8.19 1 1 7/8 _

2-MSS-026-44-1 8.13, 8.14, 8.19 1 2 1/2 ,,

2-MSS-026-44-1 8.13, 8.14, 8.19 7 7/8 _

2-MSS-026-44-1 8.13, 8.14,8.19 1 7 3/4 _

2-MSS-026-44-1 8.13, 8.14, 8.19 0 3/4 ',

2-MSS-026-44-1 8.13, 8.14, 8.19 8 11 _ __

2-MSS-026-44-1 8.13, 8.14, 8.19 1 3 1/8 -

2-MSS-026-44-1 8.13, 8.14, 8.19 8 0  : 1/2 i 2-MSS-026-44-1 8.13, 8.14, 8.19 90 3 3  :

2-MSS-026-44-1 8.13, 8.14, 8.19 i 3 3 i 2-MSS-026-44-1 8.13, 8.14, 8.19  : 7 _

2-MSS-026-44-1 8.13, 8.14, 8.19 _ 10  : 1/8 2-MSS-026-44-1 8.13, 8.14, 8.19 _ 7 4  : 5/8 2-MSS-026-44-1 8.13,8.14,8.19 1 5 3/4 2-MSS-026-44-1 8.13, 8.14, 8.19 i 12 1 3/8 2-MSS-026-44-1 8.13, 8.14, 8.19 33 11 _3/8 2-MSS-026-44-1 8.13, 8.14, 8.19 18 1 ___

2-MSS-026-44-1 8.13, 8.14, 8.19 __ 1 4 ___

2-MSS-026-44-1 8.13, 8.14, 8.19 90 3 31 ,

2-MSS-026-44-1 8.13, 8.14,8.19 2 11 1/2 1 4 ,

2-MSS-026-44-1 8.13, 8.14, 8.19 3 1/2 3 3 ,

2-MSS-026-44-1 8.13, 8.14, 8.19 _11- 5/8 _

2-MSS-026-44-1 8.13, 8.14, 8.19 7 _

D:\CaIc File\H21 C-093 Rev OOO.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 12 Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5Y7104 Glenn Stinson / 7/30/04 H21 C-093 00 Table 4.1-5 Main Steam Line B Interstitial Pipe Data MSL "B" Interstitial Piping Between IVs Starting Location: MSIV 2MSS*AOV6B Stopping Location: MSIV 2MSS*AOV7B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet inches 2-MSS-026-151-1 8.14, 8.20, 8.28 1 5 3/4  :

2-MSS-026-151-1 8.14, 8.20, 8.28 15 4 9/16 _

2MSS-026-151-1 8.14, 8.20, 8.28 _3 10 :7/8 2-MSS-026-151-1 8.14, 8.20, 8.28 _781 3 00 Table 4.1-6 Main Steam Line B Outboard Pipe Data MSL "B" Piping After Outboard IV Starting Location: MSIV 2MSS*AOV7B Stopping Location: 4'0" before 2MSS-MSV1 B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-028-3-4 8.28, 8.21 90 32 8 _

2-MSS-028-3-4 8.28, 8.31 3 6 2-MSS-028-3-4 8.28, 8.31 __3 11 1/8 2-MSS-028-3-4 8.28, 8.31 4 5  ; 5/8 2-MSS-028-3-4 8.28, 8.31 __1 1  : 7/8 2-MSS-028-3-4 8.28, 8.31 __14 9 5/8 2-MSS-028-3-4 8.28, 8.31 __9 9 5/8 2-MSS-028-3-4 8.28, 8.31 __3 11 1/2 2-MSS-028-3-4 8.28, 8.31 90 _ _ 3 6  :

2-MSS-028-3-4 8.28, 8.31 3 6  : i 2-MSS-028-3-4 8.28, 8.31 2 2 3/8 -

2-MSS-028-3-4 8.28, 8.31 6 4 1/4  :

2-MSS-028-3-4 8.28, 8.31 2 9 5/8 _

2-MSS-028-3-4 1 8.28, 8.31 2 2 1/4 _

2-MSS-028-4-4 1 8.30, 8.32 28 6  ; i

1. Includes length through 48" main steam header.

D:.\Calc File\H21 C-093 Rev O00.doc

LNUCLEA ENGINEERING CALCULATION CONTINUAT SHEET IPage 13I Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision 1 Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 Ref.

Table 4.1-7 Main Steam Line C Inboard PiMe Data MSL "C" Piping Leading Up To Inboard IV Starting Location: Reactor Stopping Location: MSIV 2MSS*AOV6C Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-026-45-1 8.15, 8.16, 8.19 2 10 1/4 _

2-MSS-026-45-1 8.15, 8.16, 8.19 90 3 3  : i 2-MSS-026-45-1 1 8.15, 8.16, 8.19  : 3 3 2-MSS-026-45-1 8.15, 8.16, 8.19 ', 4 9 1/2 2-MSS-026-45-1 8.15, 8.16, 8.19 _ 3 6  : 3/4 2-MSS-026-45-1 8.15, 8.16, 8.19 i 10 1 3/8 2-MSS-026-45-1 8.15, 8.16, 8.19 _ 6 i 1/2 2-MSS-026-45-1 8.15, 8.16, 8.19 45 _ _ 1 4 3/16 2-MSS-026-45-1 8.15, 8.16, 8.19 __ 1 4 3/16 2-MSS-026-45-1 8.15, 8.16, 8.19 i 1 10 1/4 2-MSS-026-45-1 8.15, 8.16, 8.19 90  : 3 3 ',

0 2-MSS-026-45-1 2-MSS-026-45-1 2-MSS-026-45-1 8.15, 8.16, 8.19 8.15, 8.16, 8.19 8.15, 8.16, 8.19 3

1 3

11 7

1/4 7/8 2-MSS-026-45-1 8.15, 8.16, 8.19 2 0 3/4 _

2-MSS-026-45-1 8.15,8.16,8.19 3/8 2-MSS-026-45-1 8.15, 8.16, 8.19 2 3 5/8 _

2-MSS-026-45-1 8.15, 8.16, 8.19 ___ ______ 7/8 ___

2-MSS-026-45-1 8.15, 8.16, 8.19 1 3 3/8 i 2-MSS-026-45-1 8.15, 8.16, 8.19 2 7/8 _

2-MSS-026-45-1 8.15, 8.16, 8.19 1 11 1/8 -

2-MSS-026-45-1 8.15, 8.16, 8.19 __ 2 4 1/2 ___

2-MSS-026-45-1 8.15, 8.16, 8.19 9 i  :

2-MSS-026-45-1 8.15, 8.16, 8.19 10 1/2 -

2-MSS-026-45-1 8.15, 8.16, 8.19 8 4 3/4 ',

2-MSS-026-45-1 8.15, 8.16, 8.19 90 3 3 ______

2-MSS-026-45-1 ___8.15, 8.16, 8.19 __ ___ 3 3 ___

2-MSS-026-45-1 8.15, 8.16, 8.19 _______1 3 5/8 2-MSS-026-45-1 8.15,8.16,8.19 3 2-MSS-026-45-1 8.15, 8.16, 8.19 7 2 1/2 2-MSS-026-45-1 ___8.15, 8.16, 8.19 ______ ___ 2 7 -43/4 2-MSS-026-45-1 8.15, 8.16, 8.19 1011 5/8 2-MSS-026-45-1 8.15, 8.16, 8.19 4 34 1 5 3/4 2-MSS-026-45-1 8.15, 8.16, 8.19 6 "20 1/2 2-MSS-026-45-1 8.15, 8.16, 8.19 i 1 3 1/2 2-MSS-026-45-1 8.15, 8.16, 8.19 90 3 2-MSS-026-45-1 8.15, 8.16, 8.19 2 11 1/2 7 2  :

2-MSS-026-45-1 8.15, 8.16, 8.19 1__ 3 1/2 3 D:\Calc File\H21C-093 Rev 000.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 14 }

0 SOriginator/Date Project:Nine Mile Point Nuclear Station Reviewer/Date Unit: 2 CalculationNo.

Disposition: N/A Revion Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00

-1eT.

MSL "C" Piping Leading Up To Inboard IV Starting Location: Reactor Stopping Location: MSIV 2MSS*AOV6C Bends Horizontal Length Vertical Length Pipe Segment Note Reference - (deg) Feet Inches Feet Inches 2-MSS-026-45-1 8.15, 8.16, 8.19 11 3/4 F 2-MSS-026-45-1 8.15, 8.16, 8.19 6 3/8 Table 4.1-8 Main Steam Line C Interstitial Pipe Data MSL "C" Interstitial Piping Between IVs Starting Location: MSIV 2MSS*AOV6C Stopping Location: MSIV 2MSS*AOV7C Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-026-154-1 8.16, 8.20, 8.28 1 7  :  :

2-MSS-026-154-1 8.16, 8.20, 8.28 15 4 5/8 _

0 2-MSS-026-154-1 2-MSS-026-154-1 8.16, 8.20, 8.28 8.16, 8.20, 8.28 3

1 T 10 1/2 Table 4.1-9 Main Steam Line C Outboard Pipe Data MSL "C" Piping After Outboard IV Starting Location: MSIV 2MSS*AOV7C Stopping Location: 4'0" before 2MSS-MSV1C Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-028-5-4 8.28, 8.21 90 32 8 -  :

2-MSS-028-5-4 8.28, 8.31 3 6 2-MSS-028-5-4 8.28, 8.31

__1 0 11/2 2-MSS-028-5-4 8.28, 8.31 ' 3 -

2-MSS-028-5-4 8.28, 8.31  ; 4 4 2-MSS-028-5-4 8.28, 8.31

_ 1 0 1/2 2-MSS-028-5-4 8.28, 8.31 ', 14 11 2-MSS-028-5-4 8.28, 8.31

" 9 10 1/2 2-MSS-028-5-4 8.28, 8.31

_ 3 11 1/8 2-MSS-028-5-4 8.28, 8.31 90 "_ 3 6 2-MSS-028-5-4 8.28, 8.31 3 6 "7_

2-MSS-028-5-4 8.28, 8.31 1 2 1 -A D:\Calc Fiel-121C-093 Rev O00.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 15 0 Project: Nine Mile Point NuclearStation Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision ,

Shane R. Gardner (CNS) /5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 HeT.

MSL "C" Piping After Outboard IV Starting Location: MSIV 2MSS*AOV7C Stopping Location: 4'0" before 2MSS-MSV1C Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches

_3/4 _

2-MSS-028-5-4 8.28, 8.31 6 4 1/8 _

2-MSS-028-5-4 8.28, 8.31 2 10 i__

2-MSS-028-5-4 1 8.28, 8.31 2 2  :

2-MSS-028-6-4 1 8.30, 8.32 28 6 i i

1. Includes length through 48" main steam header.

Table 4.1-10 Main Steam Line C Inboard Pipe Data MSL "D" Piping Leading Up To Inboard IV Starting Location: Reactor Stopping Location: MSIV 2MSS*AOV6D 0 Pipe Segment 2-MSS-026-46-1 Note Reference 8.17, 8.18, 8.19 Bends (deg)

Horizontal Length Feet Inches 2 10 1/16 Vertical Length Feet Inches 2-MSS-026-46-1 8.17, 8.18, 8.19 90 3 3 2-MSS-026-46-1 8.17, 8.18, 8.19 ', 3 3 2-MSS-026-46-1 8.17, 8.18,8.19 . 5 1 12 2-MSS-026-46-1 8.17, 8.18, 8.19 _1 7.

2-MSS-026-46-1 8.17, 8.18, 8.19 5, .4 2-MSS-026-46-1 8.17, 8.18, 8.19 9 9 1/4 2-MSS-026-46-1 8.17, 8.18, 8.19 90 9 3 9 143 2-MSS-026-46-1 8.17, 8.18, 8.19 3 3 2-MSS-026-46-1 8.17, 8.18, 8.19 2 1 1/2 2-MSS-026-46-1 8.17, 8.18, 8.19 2 5 1/8 i 2-MSS-026-46-1 1 8.17, 8.18, 8.19 5 1 1/2 "

2-MSS-026-46-1 1 8.17, 8.18, 8.19 2 4 1/4  ;

2-MSS-026-46-1 8.17, 8.18, 8.19 2 45 3/4:_

2-MSS-026-46-1 1 8.17, 8.18, 8.19 1 7 1/4 11 2-MSS-026-46-1 8.17, 8.18, 8.19 1 1 _: 1/4 2-MSS-026-46-1 8.17, 8.18, 8.19 1 2 1/8 2-MSS-026-46-1 8.17, 8.18, 8.19 2 10 2-MSS-026-46-1 8.17, 8.18, 8.19 1 3 3/4 2-MSS-026-46-1 8.17, 8.18, 8.19 90 3 .3 2-MSS-026-46-1 8.17, 8.18, 8.19  ; 3 3 2-MSS-026-46-1 8.17, 8.18, 8.19 " 3 8 2-MSS-026-46-1 8.17, 8.18, 8.19 2 4 5/8 2-MSS-026-46-1 8.17, 8.18, 8.19 2 9 D:\Calc File\H21C-093 Rev 000.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 16 Project: Nine Mile Point Nuclear Station Unit: 2- Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 HeT.

MSL "D" Piping Leading Up To Inboard IV Starting Location: Reactor Stopping Location: MSIV 2MSS*AOV6D Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-026-46-1 8.17, 8.18, 8.19  : 1 5 1/4 2-MSS-026-46-1 8.17, 8.18, 8.19 _ 2 1 7/8 2-MSS-026-46-1 1 8.17, 8.18, 8.19,, 9 3/4 2-MSS-026-46-1 8.17, 8.18, 8.19  : 21 0 :3/4 2-MSS-026-46-1 8.17, 8.18, 8.19 1 4 1/4 2-MSS-026-46-1 8.17, 8.18, 8.19 90  : 3 3 2-MSS-026-46-1 8.17, 8.18, 8.19 3 3  :  :

2-MSS-026-46-1 8.17, 8.18, 8.19 1 2  :  :

2-MSS-026-46-1 8.17, 8.18, 8.19 3 8 1/2 _

2-MSS-026-46-1 8.17, 8.18, 8.19 11 _

Table 4.1-11 Main Steam Line D Interstitial Pipe Data 0 MSL "D" Interstitial Piping Between IVs Starting Location: MSIV 2MSS*AOV6D Stopping Location: MSIV 2MSS*AOV7D Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-026-153-1 8.18, 8.20, 8.28 1 6 1/2 -

2-MSS-026-153-1 8.18, 8.20, 8.28 13 3 2-MSS-026-153-1 8.18, 8.20, 8.28 3 10 ,3/4 2-MSS-026-153-1 8.18, 8.20, 8.28 I_ II _ 1 1 0  : 1/4 Table 4.1-12 Main Steam Line D Outboard Pipe Data MSL "D"Piping After Outboard IV Starting Location: MSIV 2MSS*AOV7D Stopping Location: 4'0" before 2MSS-MSV1 D Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-028-7-4 8.28, 8.21 90 32 8  ! "

2-MSS-028-7-4 8.28, 8.31,,_ 3 6 2-MSS-028-7-4 8.28, 8.31 3 1 /

2-MSS-028-7-4 8.28, 8.31 283

',4 11 5 "

18_/2 D*\CaIc File\H-21C-093 Rev OOO.doc:

I- -

NUCLEAR ENGINEERING CALCU LATION CONTINUATION SH EET IPage 17(Nx Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 Ref, MSL "D" Piping After Outboard IV Starting Location: MSIV 2MSS*AOV7D Stopping Location: 4'0" before 2MSS-MSV1D Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches

_ ___ 3/4 2-MSS-028-7-4 8.28, 8.31 S1 1 15/8 2-MSS-028-7-4 8.28, 8.31

, 14 7 :1/4 2-MSS-028-7-4 8.28, 8.31 8 5 1

8 5 :3/8]

2-MSS-028-7-4 8.28, 8.31

___________ ______ _____ _____ 11 1/2 2-MSS-028-7-4 8.28, 8.31 4 11 i 1/

... ;4 5  :,3/4 2-MSS-028-7-4 8.28, 8.31 90  : 3 6 2-MSS-028-7-4 8.28, 8.31 3 6 _ i 2-MSS-028-7-4 8.28, 8.31 0 2-MSS-028-7-4 8.28, 8.31 2 1 j3/4 9 1 3/4 2-MSS-028-7-4 2 8.28, 8.31 2 2 1/4 2-MSS-028-8-4 2 8.30, 8.32 28 6 ,,

2. Includes length through 48" main steam header.

C.2. Main Steam Drain Lines Table 4.2-1 Inboard Main Steam Line Drain Inboard Pipe Data MSL Inboard Drain Piping Leading Up To Inboard IV Starting Location: 2-MSS-002-048-1 /1 -MSS-006-150-1 tee Stopping Location: 2MSS*MOV1 11 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-006-150-1 8.20, 8.24 9  : i 2-MSS-006-150-1 1 8.20, 8.24 9  : _

2-MSs-006-150-1 8.20, 8.24 2  ! i 2-MSS-006-150-1 8.20, 8.24 90 3 11 _

2-MSS-006-150-1 8.20, 8.24 11 4 _  :

1. Neglects valve 2MSS*V207 length.

Table 4.2-2 Inboard Main Steam Line Drain Interstitial Pipe Data D:\Calc File\H21C-093 Rev OOO.doc

INUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET IPage "18Net)

Project:Nine Mile PointNuclear Station Unit: Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5[7/04 Glenn Stinson / 7/30/04 H21C-093 00 Rel.

MSL Inboard Drain Interstitial Piping Between IVs Starting Location: 2MSS*MOV1 11 Stopping Location: 2MSS*MOV1 12 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-006-150-1 8.20, 8.24 90 1 4 i _

2-MSS-006-150-1 8.20, 8.24 90 9 6  :

2-MSS-006-150-1 8.20, 8.24 90 2 1 ,7/8 2-MSS-006-150-1 8.20, 8.24 14 7 5/16 _

2-MSS-006-150-1 2 8.20, 8.25 2 8 ',

2. To downstream side of valve.

Table 4.2-3 Outboard Main Steam Line Drain Inboard Pipe Data MSL Outboard Drain Piping Leading Up To Inboard IV Starting Location: 2-MSS-750-168-1/2-MSS-002-175-2 tee Stopping Location: 2MSS*MOV208 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-MSS-002-175-2 8.20, 8.28, 8.29 4 8  :

MSS-002-175-2 8.20, 8.28, 8.29 90. 5 5 :1 2-MSS-002-175-2 1 8.20, 8.28, 8.29 1 5 5 5 11 :1/2 _ ,

1. To center of valve 4.3. Drywell Drains Table 4.3-i Drywell Floor Drain Inboard Pipe Data Drywell Floor Drain Piping Leading Up To Inboard IV Starting Location: 2-DFR-006-65-2/2-DFR-004-66-2 tee Stopping Location: 2DFR*MOV121 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-DFR-006-65-2 8.47, 8.54, 8.55 8.58 6 9 :9/16 2-DFR-006-65-2 1 8.47, 8.54, 8.55, 8.58 90 2 4 3/4 _

2-DFR-006-65-2 8.47, 8.54, 8.55 8.58 4 1/8 ',

2-DFR-006-65-2 2 8.47, 8.54, 8.55, 8.55, 8.58 1 1 1/8 _

D:\Calc File\H21C-093 Rev OO0.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 19 0 Project:Nine Mile Point Nuclear Station Originator/Date Reviewer/Date Unit: 22 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 Ref.

1. Neglects 2DFR*V114 valve length.

2. To valve edge.

Table 4.3-2 Drywell Floor Drain Interstitial Pipe Data Drywell Floor Drain Interstitial Piping Between IVs Starting Location: 2DFR*MOV121 Stopping Location: 2DFR*MOV1 20 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-DFR-006-25-2 2 8.54, 8.58 7 3  ::

2-DFR-006-25-2 2 8.54, 8.58 11 22 5/16

2. To valve edge.

Table 4.3-3 Drywell Floor Drain Tank Vent Interstitial Pipe Data Drywell Floor Drain Tank Vent Interstitial Piping Between IVs Starting Location: 2DFR*MOV140 0 Stopping Location: 2DFR*MOV139 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-DFR-003-52-2 8.54,8.57 1 5 7/8 _

2-DFR-003-52-2 8.54,8.57 1 5/8 _

2-DFR-003-52-2 8.54,8.57 90 4 1/2 2-DFR-003-52-2 8.54,8.57 904 1/ 4 1/2 2-DFR-003-52-2 8.54,8.57 664 1/4 2-DFR-003-52-2 8.54,8.57 90 4 1/2 2-DFR-003-52-2 8.54,8.57 904 1/2 2-DFR-003-52-2 8.54,8.57 1 3/4 _

2-DFR-003-52-2 8.54,8.57 8 6 3/4 _

2-DFR-003.56-2 8.54,8.57 __ 4 3 ____ ___ __

2-DFR-003-56-2 8.54,8.57 88 2 '

2-DFR-003-56-2 8.54,8.57 2 " _

2-DFR-003-56-2 ___ 8.54,8.57 90 4 1/2 _ ______

2-DFR-003-56-2 8.54,8.57 84 1/2 2-DFR-003-56-2 8.54,8.57 _ 1 1

2-DFR-003-56-2 8.54,8.57 908 4_1/21/4 2-DFR-003-56-2 ___8.54,8.57 ___ __ 8 7/8 2-DFR-003-56-2 8.54,8.57 :4 3 5/8 2-DFR-003-56-2 8.54,8.57 90 4 1/2 2-DFR-003-56-2 8.54,8.57 _4 1/2 81/

2-DFR-003-56-2 8.54,8.57 8 7/88 ,7/

2-DFR-003-56-2 8.54,8.57 1 2 1/2 i D:\Calc Flie\H21C-093 Rev 000.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 20 (Next Project:Nine Mile PointNuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 RTef.

Table 4.3-4 Drvwell EauiDment Drain Inboard Pipe Data Drywell Equipment Drain Piping Leading Up To Inboard IV Starting Location: 2-DER-004-18-2/2-DER-004-17-2 tee Stopping Location: 2DER*MOV119 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-DER-004-18-2 8.47, 8.53 90 ', 8 2 13/16 2-DER-004-18-2 8.47, 8.53 90 19 11 3/8 2-DER-004-18-2 8.47, 8.53 90 ,, 4 3 ,_ 7/8 2-DER-004-18-2 1 8.47, 8.53 3 6 '- _

2-DER-004-18-2 8.47, 8.53 2 6 1/2 "

1. Neglects 2DER*V300 valve length Table 4.3-5 Drvwell Eauipment Drain Interstitial Pipe Data Drywell Equipment Drain Interstitial Piping Between IVs Starting Location: 2DER*MOV1 19 Stopping Location: 2DER*MOV120 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-DER-004-13-2 8.47, 8.53 9 8 1/2 2-DER-004-14-2 8.47, 8.53 4 2 1/2 Table 4.3-6 Drywell Equipment Drain Tank Vent Inboard Pipe Data Drywell Equipment Drain Tank Vent Piping Leading Up To Inboard IV Starting Location: Drywell Atmosphere Stopping Location: 2DER*MOV130 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-DER-002-34-2 8.47, 8.48 6 2-DER-002-34-2 1 8.47, 8.48 135 1 2 9/16

1. To center of valve.

Table 4.3-7 Drywell Equipment Drain Tank Vent Interstitial Pipe Data D:\Calc File\H21C-093 Rev O00.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 21 (Next Project: Nine Mile PointNuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 ret.

Drywall Equipment Drain Tank Vent Interstitial Piping Between IVs Starting Location: 2DER*MOV130 Stopping Location: 2DER*MOV131 (QA CAT 1 Boundary)

Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-DER-002-34-2 8.47, 8.48 7 13/16 2-DER-002-34-2 8.47, 8.48 21 1 4 5/8 2-DER-002-34-2 8.47,8.49 6 4 3/16 4.4. Feedwater Lines Table 4.4-1 Feedwater Lune A Inboard Pipe Data Feedwater Line A Piping Leading Up To Inboard IV Starting Location: 24"x18" reducer on 2-FWS-024-61-1 Stopping Location: 2FWS*V12A ......

0 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-FWS-024-61-1 8.40, 8.42 1 4 3/4 2-FWS-024-61-1 8.40, 8.42 1 5  : _

2-FWS-024-61-1 8.40, 8.42 7 1 1/8  :

2-FWS-024-61-1 1 8.40, 8.42 16 9 ', 5/8  :

2-FWS-024-61-1 8.40, 8.42 10 1/8 _

2-FWS-024-61-1 8.40, 8.42 4 8 1/2 _

2-FWS-024-61-1 8.40, 8.42 1 3 3/8 _

2-FWS-024-61-1 8.40, 8.42 9 1/4 _

2-FWS-024-61-1 1 8.40, 8.42 47 1 3 _ i 2-FWS-024-61-1 8.40, 8.42 1 3 _ i 2-FWS-024-61-1 1,2 8.40,8.42 90 1 6  : 3/4 2-FWS-024-31-1 8.40, 8.42 _ 7 11/2 2-FWS-024-31 -1 8.40, 8.42 _ 1 _ 3/8 2-FWS-024-31 -1 8.40, 8.42 _ 11 3 _

2-FWS-024-31-1 8.40, 8.42 ' 2 1 2-FWS-024-31 -1 8.40, 8.42 i 7 5 5/8 2-FWS-024-31-1 8.40, 8.42 _ 2 4 1/4 2-FWS-024-31-1 8.40, 8.42  ; 5 10 3/8 2-FWS-024-31-1 8.40, 8.42 90  : 2 2-FWS-024-31 -1 8.40, 8.42 2 i  !

2-FWS-024-31 -1 8.40, 8.42 1 2 1/8 -

2-FWS-024-31 -1 8.40, 8.42 1 9 7/8

1. Conservative angle approximation.

2. 2FWS*HCV54A valve length neglected.

D:\Calc File\H21 C-093 Rev O0O.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 22 0 Project:Nine Mile Point Nuclear Station Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 Ret, Table 4.4-2 Feedwater Line A Interstitial Pipe Data Interstitial Piping Between IVs Starting Location: 2FWS*V12A Stopping Location: 2FWS*AOV23A Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-FWS-024-31-1 3 8.40, 8.42 11 10 5/16 2-FWS-024-31-1 8.40, 8.42 11 i 1/2 2-FWS-024-31-1 8.40, 8.42 1 1/4

3. Assumes the lengtn o0Z-41 on I-eeawater line u.

Table 4.4-3 Feedwater Line A Outboard Pipe Data

. Piping After Outboard IV Starting Location: 2FWS*AOV23A Stopping Location: 2FWS*MOV21A Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-FWS-024-50-1 8.40, 8.42 1 10 1/4 _

2-FWS-024-50-1 8.40, 8.42 3 9 3/4 2-FWS-024-50-1 8.40, 8.42 3 10 i 2-FWS-024-50-1 8.40, 8.42 1 1 !1/2 2-FWS-024-50-1 8.40, 8.42 11 3/8 -

2-FWS-024-50-1 8.40, 8.42 8 1/4 ',

Table 4.4-4 Feedwater Line B Inboard Pipe Data Feedwater Line B Piping Leading Up To Inboard IV Starting Location: 24"x18" reducer on 2-FWS-024-60-1 Stopping Location: 2FWS*V12B D:\CaIc File\-21 C-093 Rev O00.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 23 (Next 0 Project: Nine Mile Point Nuclear Station Originator/Date Reviewer/Date Unit: _2_

Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 l*ef.1 13ends Horizontal Lenoth Vertical Lenath Pipe Segment Note Reference (deg) Feet Iinches Feet I Inches 2-FWS-024-60-1 8.40, 8.45 1 5 5/8 _

2-FWS-024-60-1 1 8.40, 8.45 16 1 6 5/8 2-FWS-024-60-1 8.40, 8.45 5_5 5-i 2-FWS-024-60-1 8.40, 8.45 1 1 3/8 _

2-FWS-024-60-1 8.40, 8.45 8 8 ___

2-FWS-024-60-1 8.40, 8.45 10 -

2-FWS-024-60-1 8.40, 8.45 1 1 1/2 2-FWS-024-60-1 1 8.40, 8.45 47 1 3 ,,

2-FWS-024-60-1 8.40, 8.45 1 3 _  :

2-FWS-024-60-1 1, 2 8.40,-8.45 90 1 6 3/8 2-FWS-024-32-1 8.40, 8.45 i 6 1/4 2-FWS-024-32-1 8.40, 8.45 i 1,_

2-FWS-024-32-1 8.40, 8.45 ' 11 4 1/8 2-FWS-024-32-1 8.40, 8.45," 2 1 1/8 2-FWS-024-32-1 8.40, 8.45  : 7 6  :

2-FWS-024-32-1 8.40, 8.45 ', 2 4 3/4 0 2-FWS-024-32-1 2-FWS-024-32-1 8.40, 8.45 8.40, 8.45 90

', 5 2

9 1/4 2-FWS-024-32-1 8.40, 8.45 2 ' ',

2-FWS-024-32-1 8.40, 8.45 1 1 3/4 _

2-FWS-024-32-1 8.40,8.45 1 10 3/8 _

1. Conservative angle approximation.

2. 2FWS*HCV54A valve length neglected.

Table 4.4-5 Feedwater Line B Interstitial Pipe Data Feedwater Line B Interstitial Piping Between IVs Starting Location: 2FWS*V12B Stopping Location: 2FWS*AOV23B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-FWS-024-32 8.40, 8.45 11 10 5/16 2-FWS-024-32-1 8.40, 8.45 11 ,

2-FWS-024-32-1 8.40, 8.45 1  : 1/2 Table 4.4-6 Feedwater Line B Outboard Pipe Data Feedwater Line B Piping After Outboard IV Starting Location: 2FWS*AOV23B 0 Stopping Location: 2FWS*MOV21B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-FWS-024-51-1 8.40, 8.45 1 10 D:\CaIc File\H21C-093 Rev O00.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 24 0 Project:Nine Mile Point Nuclear Station Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 Ret.

Feedwater Line B Piping After Outboard IV Starting Location: 2FWS*AOV23B Stopping Location: 2FWS*MOV21B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-FWS-024-51-1 8.40, 8.45 3 10 1/4 _

2-FWS-024-51 -1 8.40, 8.45 5 10 __ _ ,

2-FWS-024-51-1 8.40, 8.45 1 1 1/4 _

2-FWS-024-51-1 8.40, 8.45 =1 1 1/2 -

2-FWS-024-51-1 8.40, 8.45 6 1/8 ',

4.5. Primary Containment Purge (CPS) Lines in Drywell/Wetwell Table 4.5-1 2" CPS Line in Drywell Inboard Pipe Data 2" CPS Line in Drywell Piping Leading Up To Inboard IV Starting Location: Drywell Atmosphere 2CPS*S03 Stopping Location: 2CPS*SOV122 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CPS-002-30-2 8.60, 8.61 4 2-CPS-002-30-2 1 8.60, 8.61 8___',

1. To center of valve.

Table 4.5-2 2" CPS Line in Drvwell Interstitial Pipe Data 2" CPS Line in Drywell Interstitial Piping Between IVs Starting Location: 2CPS*SOV122 Stopping Location: 2CPS*SOV120 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (de)g Feet Inches Feet Inches 2-CPS-002-30-2 8.60, 8.61 2 6  : _

2-CPS-002-30-2 8.60, 8.61 5 45 1/16_ _

2-CPS-002-19-2 8.60, 8.61 55 1/21 2-CPS-002-19-2 8.60, 8.61 8 1/2 ,

1. 1o center of valve.

D:\Calc Fda\H21C-093 Rev 000.doc

NUCLEAR ENGINEERING 'CALCULATION CONTINUATION I SHEET Page (Next 2

0 Project: Nine Mile PointNuclea" Station Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 ef. Table 4.5-3 14" CPS Line in Drywell Inboard Pipe Data 14" CPS Line In Drywell Piping Leading Up To Inboard IV Starting Location: Drywell Atmosphere (2CPS*S01A)

Stopping Location: 2CPS*AOV106 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet I Inches 2-CPS-14-35-2 8.60, 8.62 1 2 Table 4.5-4 14" CPS Line in Drywell Interstitial Pipe Data 14" CPS Line in Drywell Interstitial Piping Between IVs Starting Location: 2CPS*AOV106 Stopping Location: 2CPS*AOV104 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CPS-14-16-2 8.60, 8.62 4 7/8 "

0 2-CPS-14-16-2 2-CPS-14-2-2 2-CPS-14-2-2 8.60, 8.62 8.60, 8.62 8.60, 8.62 8

1 6

i  :

__1 11 8 :7/8 "

Table 4.5-5 12" CPS Line in Wetwell Inboard Pipe Data 12" CPS Line in Wetwell Piping Leading Up To Inboard IV Starting Location: Wetwell Atmosphere (2CPS*S02A)

Stopping Location: 2CPS*AOV107 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CPS-01 2-36-2 8.60, 8.63

"_5 9 1/8 2-CPS-01 2-36-2 8.60, 8.63 i 1 2-CPS-012-36-2 8.60, 8.63 90 1  : _

0 F 2-CPS-012-36-2 8.60, 8.63 3 8 "55/8_

D:\Calc File\H21C-093 Rev O00.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 26 (Next )

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5f/104 Glenn Stinson / 7/30/04 H21 C-093 00 Ref.1 Table 4.5-6 12" CPS Line in Wetwell Interstitial Pipe Data 12" CPS Line In Wetweli Interstitial Piping Between IVs Starting Location: 2CPS*AOV107 Stopping Location: 2CPS*AOV105 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CPS-012-15-2 8.60, 8.63 4 1/4  :

2-CPS-012-15-2 8.60, 8.63 7. 3 ,

2-CPS-012-3-2 8.60, 8.63 2 6 2-CPS-012-3-2 8.60, 8.63 10 1/4 Table 4.5-7 2" CPS Line in Wetwell Inboard Pipe Data 2" CPS Line In Wetwell Piping Leading Up To Inboard IV Starting Location: Wetwell Atmosphere (2CPS*SO4)

Stopping Location: 2CPS*SOV121 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet 1 inches 2-CPS-002-16-2 1 8.60, 8.64 1 9 1/2 1

1. To center of valve Table 4.5-8 2" CPS Line in Wetwell Interstitial Pipe Data 2" CPS Line In Wetwell Interstitial Piping Between IVs Starting Location: 2CPS*SOV121 Stopping Location: 2CPS*SOV1 19 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CPS-002-16-2 8.60, 8.64 2 5 1/2 2-CPS-002-10-2 2 8.60, 8.64 90 5 2-CPS-002-10-2 8.60, 8.64 90 4 6 2-CPS-002-10-2 8.60, 8.64 90 3 9  : -

2-CPS-002-10-2 1 8.60, 8.64 90 6 2 _, _

1. To center of valve

2. Conservatively assumes 5 ft. length through penetration D:\Calc File\H21C-093 Rev OOO.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 27i....__

(Nextj 0 Project: Nine Mile Point Nuclear Station Originator/Date I Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7104 Glenn Stinson / 7/30/04 H21C-093 00 Ref, 4.6. Reactor Water Cleanup (RWCU) Line Table 4.6-1 RWCU Line Inboard Pipe Data RWCU Piping Leading Up To Inboard IV Starting Location: 2-WCS-008-86-1/2-WCS-004-3-1 tee Stopping Location: 2WCS*MOV102 .....

Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-WCS-008-86-1 8.34, 8.37 6 2-WCS-008-86-1 8.34, 8.37 6 4 3/8 -

2-WCS-008-86-1 8.34,8.37 2-WCS-008-86-1 8.34, 8.37 3 2 1/2 Table 4.6-2 RWCU Line Interstitial Pipe Data RWCU Interstitial Piping Between IVs Starting Location: 2WCS*MOV102 0 Stopping Location: 2WCS*MOV1 12 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-WCS-008o86-1 8.34, 8.37 1 3 2-WCS-008-86-1 8.34, 8.37 .10 8 2-WCS-008-87-1 8.34, 8.37 1 3 '1 4.7. Post Accident Sampling System (PASS) Lines Table 4.7-1 PASS Sample Line A Inboard Pipe Data Piping Leading Up To Inboard IV Starting Location: Penetration Z60B Stopping Location: 2CMS*SOV74A Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CMS-750-61-2 1, 2 8.89, 8.91 0 16 1/2  :

2-CMS-750-61-2 2 8.89, 8.91 45 1 8 0 2-CMS-750-61-2 8.89, 8.91 45 " 8 1/2 2-CMS-750-61-2 8.89, 8.91 90  : 5 3 2-CMS-750-61-2 8.89, 8.91 90 3 8 5/8 2-CMS-750-61-2 8.89, 8.91 90  : 5 6 7/8 DACalc File\H21C-093 Rev 000.doc

NULEA ENGINEERING CALCULATION COONTINU SHEET IPage N 2x 0 Project: Nine Mile PointNuclear Station Originator/Date IReviewer/Date Unit: 2_

Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 OrgntrDteRvee/at

_aln~.Rvso Ret.

Piping Leading Up To Inboard IV Starting Location: Penetration Z60B Stopping Location: 2CMS*SOV74A .....

Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet inches 2-CMS-750-61-2 8.89, 8.91 90 5 5 i "

2-CMS-750-61-2 8.89, 8.91 90 ', 21 11 1/8 2-CMS-750-61-2 8.89, 8.91 90 4 6 1/2 _

2-CMS-750-61-2 8.89, 8.91, 8.92 30 " 4 5 3/16 2-CMS-750-61-2 8.89, 8.92 120 ' 2 i 2-CMS-750-61-2 8.89, 8.92 4 7 13/16 2-CMS-750-61-2 8.89, 8.92 2 6  :

2-CMS-750-61-2 8.89, 8.92 90 6 _  ;

2-CMS-750-77-2 8.89, 8.100 6 __

2-CMS-750-77-2 8.89, 8.100 3 1 ', _

2-CMS-750-77-2 2 8.89, 8.100 1 10  !  :

0 1. Includes piping in penetration.

2. Includes length through SOV(s).

Table 4.7-2 PASS Sample Line A Interstitial Pipe Data Interstitial Piping Between IVs Starting Location: 2CMS*SOV74A Stopping Location: 2CMS*SOV76A Bends Horizontal Length Vertical Leng th Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CMS-750-77-2 2 8.89, 8.100 1

2. Includes length through SOV(s).

Table 4.7-3 PASS Sample Line B Inboard Pipe Data Piping Leading Up To Inboard IV Starting Location: Penetration Z60F Stopping Location: 2CMS*SOV74B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CMS-750-69-2 1 8.89, 8.93 8 i 9/16 2-CMS-750-69-2 8.89, 8.93 _ _3/4 2-CMS-750-69-2 2 8.89, 8.93 _: 6 1/2 D:\Calc File\H2iC-093 Rev O0O.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 29 (Next 0 Project: Nine Mile Point NuclearStation Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 517104 Glenn Stinson / 7/30/04 H21 C-093 00 let.

Piping Leading Up To Inboard IV Starting Location: Penetration Z60F Stopping Location: 2CMS*SOV74B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CMS-750-69-2 8.89, 8.93 90 1 3 15/16 i 2-CMS-750-69-2 8.89, 8.93 90 2 10 3/8 _

2-CMS-750-69-2 8.89, 8.93 90 6 1 1/4 '

2-CMS-750-69-2 8.89, 8.93 90 3 ',  :

2-CMS-750-69-2 8.89, 8.93 90 _ 3 3 1/2 2-CMS-750-69-2 8.89, 8.93 90 3 4 1/2 _,

2-CMS-750-69-2 8.89, 8.93 45  ; 2 _ 1/16 2-CMS-750-69-2 8.89, 8.93 90 6 7 3/8 _

2-CMS-750-69-2 8.89, 8.93 90 _ 1 8 i 2-CMS-750-69-2 8.89, 8.93 45 7  : 1/16 _

2-CMS-750-69-2 8.89, 8.93 90 8 5 5_

2-CMS-750-69-2 8.89, 8.93 45 _ 11 5/16 2-CMS-750-69-2 8.89, 8.93 90 5 2 2-CMS-750-69-2 8.89, 8.93 90 1 3 _

2-CMS-750-69-2 8.89, 8.93 90 10 7 1/2 _

2-CMS-750-69-2 8.89, 8.93 _ 5 5 2-CMS-750-69-2 8.89, 8.94 45 , 5 3  :

2-CMS-750-69-2 8.89, 8.94 45 __1 9 1 3/16 2-CMS-750-69-2 8.89, 8.94 57 8 4 -

2-CMS-750-69-2 8.89, 8.94 11 6 i, 2-CMS-750-69-2 8.89, 8.94 45 1 6  :  :

2-CMS-750-69-2 8.89, 8.94 45 _,, 1 ..... 3/4 2-CMS-750-69-2 8.89, 8.94 45 5 1  :  :

2-CMS-750-69-2 8.89, 8.94 45 _ 2 7 1/8 2-CMS-750-69-2 8.89, 8.94 90 3 4 2-CMS-750-69-2 8.89, 8.94 4.5 _, 6 11,_

2-CMS-750-69-2 8.89, 8.94 45 ', 6 15/16 2-CMS-750-69-2 8.89, 8.94 45 _ 4 4 7/8 2-CMS-750-69-2 8.89, 8.94 45 _ 4 1/4 2-CMS-750-69-2 8.89, 8.94 9 6 2-CMS-750-69-2 8.89, 8.95 45 11 3/4 2-CMS-750-69-2 8.89, 8.95 45 5 5/16 2-CMS-750-69-2 8.89, 8.95 90 6 :

2-CMS-750-69-2 8.89, 8.95 5 3/4 2-CMS-750-69-2 8.89, 8.96 90 3 2-CMS-750-79-2 8.89, 8.96, 8.100 90 4 0.4898 2-CMS-750-79-2 8.89, 8.100 90 5 11 3/4

.2-CMS-750-79-2 2 8.89, 8.100 2 10 D:\Calc File\H21C-093 Rev O00.doc

NUCEA ENGINEERING CALCULATION CONTINUATIO SHEET Pageo ot _30 0 Project:Nine Mile Point Nuclear Station Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 ReT.

Piping Leading Up To Inboard IV Starting Location: Penetration Z60F Stopping Location: 2CMS*SOV74B Bends Horizontal Lenath I Vertical Lenath Pipe Segment Note Reference (deg) Feet I Inches I Feet I Inches

1. Includes piping in penetration.

2. Includes length through SOV(s).

Table 4.7-4 PASS Sample Line B Interstitial Pipe Data Interstitial Piping Between lVs Starting Location: 2CMS*SOV74B Stopping Location: 2CMS*SOV76B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CMS-750-79-2 2 8.89, 8.100 6 I I 2-CMS-750-79-2 2 8.89, 8.100 6_

2. Includes length through SOV(s).

Table 4.7-5 PASS Return Line A Inboard Pipe Data Piping Leading Up To Inboard IV Starting Location: Penetration Z60D Stopping Location: 2CMS*SOV75A Bends Horizontal Length Vertical Length Pipe Segment Note Reference (de9L Feet Inches Feet Inches 2-CMS-750-2-2 1 8.89, 8.97 1 1 : i 2-CMS-750-2-2 8.89, 8.97 45 6 _ __

2-CMS-750-2-2 8.89, 8.97 45 2 1 2-CMS-750-2-2 8.89, 8.97 90 5 1 1/4 _

2-CMS-750-2-2 8.89, 8.97 90 4 10 9/16 _ _ _

2-CMS-750-2-2 8.89, 8.97 90 _ 13 9 11/16 2-CMS-750-2-2 8.89, 8.97 90 6 2  : _ _

2-CMS-750-2-2 8.89, 8.97 90 _ 2 66 2-CMS-750-2-2 8.89, 8.97 90 13 10 1/8 2-CMS-750-2-2 8.89, 8.97 90  : 2 5 3/8 2-CMS-750-2-2 8.89, 8.97 29 21 11 1/2 -

2-CMS-750-2-2 8.89,8.97 90 8 9/16 2-CMS-750-2-2 8.89, 8.97 36 _ 20 10 7/16 2-CMS-750-2-2 8.89, 8.97 36 1 5 15/16 2-CMS-750-2-2 8.89, 8.97  : 1 2 15/16 2-CMS-750-2-2 8.89, 8.98 13 , 4 9 D:\Calc File\H21 C-093 Rev 000.doc

INUCLEAR ENGINEERING CALCULATION CONTINUAT SHEET IPage] 31 0 Project:Nine Mile PointNuclear Station Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 r.'" -

HeT.

Piping Leading Up To Inboard IV Starting Location: Penetration Z60D Stopping Location: 2CMS*SOV75A Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CMS-750-2-2 8.89, 8.98 90  : 9 0.2622 2-CMS-750-63-2 8.89, 8.98 2 13/16 2-CMS-750-63-2 8.89, 8.99 90 3 5/8 _

2-CMS-750-78-2 8.89, 8.99 2 ,,i _

2-CMS-750-78-2 8,89,8.100 90 9 -

2-CMS-750-78-2 8.89, 8.100 90 6 8 1/8 ,,,,

2-CMS-750-78-2 2 8.89,8.100 1 9 ', i

1. From outer edge of penetration.

2. Includes length through SOV(s).

Table 4.7-6 PASS Return Line A Interstitial Pipe Data Interstitial Piping Between IVs Starting Location: 2CMS*SOV75A Stopping Location: 2CMS*SOV77A Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CMS-750-78-2 2 8.89, 8.100 6 i i 2-CMS-750-78-2 2 8.89, 8.100 6  :

2. Includes length through SOV(s).

Table 4.7-7 PASS Return Line B Inboard Pipe Data Piping Leading Up To Inboard IV Starting Location: Penetration Z60H Stopping Location: 2CMS*SOV75B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CMS-750-71-2 1 8.89, 8.101 _ 3/4 _

2-CMS-750-71-2 8.89, 8.101 1 i i 2-CMS-750-71-2 8.89, 8.101 45 1 , 3/4 2-CMS-750-71-2 8.89, 8.101 45 1 11 ', __

2-CMS-750-71-2 8.89, 8.101 90 1 4 2 2-CMS-750-71-2 8.89, 8.101

__8 6 1/4 2-CMS-750-71-2 8.89, 8.102 90 ' 9 4 5/8 D:\Calc FileNH21C-093 Rev OOO.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 32 (Next )

0 Project: Nine Mile Point Nuclear Station Originator/Date Reviewer/Date Unit: Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) /5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 Ref.

Piping Leading Up To Inboard IV Starting Location: Penetration Z60H Stopping Location: 2CMS*SOV75B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CMS-750-71-2 8.89, 8.102 90 1 i 2-CMS-750-71-2 8.89, 8.102 90 1 7  ;

2-CMS-750-71-2 8.89,8.102 90 3 2-CMS-750-71-2 8.89, 8.102 90 ,, 5 1 1/4 2-CMS-750-71-2 8.89, 8.102 30 3 6 i 2-CMS-750-71-2 8.89, 8.102 30 3 10 ___

2-CMS-750-71-2 8.89, 8.102 90 12 11 3/16 2-CMS-750-80-2 8.89, 8.102 45 _ _6 2-CMS-750-80-2 8.89, 8.91 45 __8 1/2 2-CMS-750-80-2 8.89, 8.91 90 1 5 i 2-CMS-750-80-2 2 8.89, 8.91 1 5 ,,  :

1. From outer edge of penetration.

2. Includes length through SOV(s).

Table 4.7-8 PASS Return Line B Interstitial Pipe Data Interstitial Piping Between lVs Starting Location: 2CMS*SOV75B Stopping Location: 2CMS*SOV77B Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CMS-750-80-2 2 8.89, 8.91 7  : j 2-CMS-750-80-2 2 8.89, 8.91 7 1

2. Includes length through SOV(s).

4.8. Instrument Air (lAS) Lines Table 4.8-1 lAS Line 1 Inboard Pipe Data Piping Leading Up To Inboard IV I Starting Location: 21AS*V179 D:\Calc File\H21 C-093 Rev 000.doc

NUCLEAR EGNRIGCALCULATION CONTINUATION SHEET Page I(Next 3*

Project:Nine Mile Point NuclearStation Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) /W57/04 Glenn Stinson / 7/30/04 H21C-093 00 lRef.1 Stopping Location: 21AS*V448 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-IAS-1 50-982-3 2 8.84, 8.87 :5/8 90 _ 10 5/8 2-lAS-1 50-982-3 8.84, 8.87 90 2 5 13/8 2-IAS-150-982-3 8.84, 8.87L_3_6_',,90 2-IAS-150-982-3 2 8.84, 8.87 1 ' _

1. Through valve 21AS*V181.

2. To center of .valve Table 4.8-2 IAS Line 1 Interstitial Pipe Data Interstitial Piping Between lVs Starting Location: 21AS*V448 Stopping Location: 21AS*SOV164 0 Pipe Segment 2-IAS-150-991-2 Note Reference 8.84, 8.87 Bends (deg)

Horizontal Length Feet Inches Vertical Length Feet Inches 61 3 7 1/2 2-lAS-150-991-2 8.84, 8.87

___61 _2 10 15/16 2-lAS-1 50-991-2 8.84, 8.87 1 11/4 _

2-IAS-150-898-2 8.84, 8.85 2 1/4 _

2-IAS-150-898-2 2 8.84, 8.85 9 1/2 - _

2. To center of SOV.

Table 4.8-3 lAS Line 2 Inboard Pioe Data Piping Leading Up To Inboard IV Starting Location: 21AS*V180 Stopping Location: 21AS*V449 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-IAS-150-780-3 1 8.74, 8.76 3 11 5/8 _

2-IAS-150-780-3 8.74, 8.76 90 i 1/2 '

2-1AS-150-780-3 8.74, 8.76 90 3 2-IAS-150-780-3 8.74, 8.76 75 3 9/16 :_

2-lAS-1 50-780-3 8.74, 8.76 90 1 4  ; i 2-lAS-1 50-780-3 8.74, 8.76 90 2 9 i ',

2-IAS-150-780-3 8.74, 8.76 90 2 9 D:\Calc File\H21C-093 Rev 000.doc

tNUCLEA ENGINEERING CALCULATION CONTINUA SHEET Page 34 0 Project:Nine Mile Point Nuclear Station Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 Ref.

Piping Leading Up To Inboard IV Starting Location: 21AS*V180 Stopping Location: 21AS*V449 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet in/hes Feet inches 2-iAS-1e50-780-3 8.74, 8.76 1 I 1/4 I

1. To center of valve.

Table 4.8-4 IAS Line 2 Interstitial Pipe Data Interstitial Piping Between IVs Starting Location: 21AS*V449 Stopping Location: 21AS*SOV165 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-IAS-1 50-779-2 8.74, 8.76 90 1 8 _

2-IAS-150-779-2 8.74, 8.76 45 1 5 5/8 2-IAS-150-779-2 8.74, 8.76 90 1 5 2-lAS-150-779-2 8.74, 8.76 1 3/8 1 8.74, 8.75 2-lAS-1 50-837-2 11 11j14

1. To center of SOV.

Table 4.8-5 IAS Line 3 Inboard Pipe Data Piping Leading Up To Inboard IV Starting Location: 21AS*V181 Stopping Location: 21AS*SOV180 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-IAS-150-714-3 1 8.77, 8.82 90 4 9 7/16 2-IAS-150-714-3 8.77, 8.82 90 22 2-IAS-150-714-3 2 8.77, 8.82 3 6 3/16

1. Termination at valve center.

2. To center of SOV.

Table 4.8-6 IAS Line 3 Interstitial Pipe Data Interstitial Piping Between IVs Starting Location: 21AS*SOV180 Stopping Location: 21AS*SOV168 I I Bends I Horizontal Length Vertical Length D:\Calc File\H-21 C-093 Rev 000.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 35

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Project:Nine Mile Point Nuclear Station Unit: 22 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) /5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 IIef, Pine Seoment Notel Reference tdea') I Feet Inches Feet I Inches 2-lAS-1 50-527-2 8.77,8.82 90 1 7 1/4 _

2-IAS-150-527-2 8.77, 8.82 90 6 5/8 _

2-IAS-150-527-2 8.77, 8.82 45  : 2 5 9/16 2-IAS-1 50-527-2 8.77, 8.82 45 _ 3 6 !1/2 2-lAS-1 50-527-2 8.77, 8.82 _4 3/4 _

2-IAS-1 50-526-2 2 8.77, 8.79 10 i

2. To center of SOV.

Table 4.8-7 IAS Line 4 Inboard Pipe Data Piping Leading Up To Inboard IV Starting Location: 21AS*V182 Stopping Location: 21AS*SOV185 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 0 2-lAS-150-521-3 2-IAS-150-521-3

1. To centerline of SOV.

1 8.77, 8.83 8.77, 8.83 1

1 4

5 5/8 1/4 Table 4.8-8 IAS Line 4 Interstitial Pipe Data Interstitial Piping Between IVs Starting Location: 21AS*SOV185 Stopping Location: 21AS*SOV167 I I i Bends I Horizontal Length Vertical Length D:\Calc File\H21C-093 Rev 000.doc

SNUCLEAR ENGINEERING CALCULATION CONTINUATION ~~~(Next SHEET Page 36 Project:Nine Mile Point NuclearStation Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5[7/04 Glenn Stinson / 7/30/04 H21 C-093 100 let Pipe Seament Note Reference (deg) Feet I Inches Feet Inches 2-lAS-150-525-3 8.77, 8.83 1 2 1/4  :

2-IAS-150-524-3 8.77, 8.78 7 6 i i 2-IAS-1 50-524-3 8.77, 8.78 90 1 7- 1/16 i 2-IAS-150-524-3 8.77, 8.78 90 _ 2 7 1/4 2-1AS-150-524-3 8.77, 8.78 90 6 9 5/8 _

2-lAS-1 50-524-3 8.77, 8.78 90 , 4 6 2-IAS-1 50-524-3 8.77, 8.78 2 3  : -

2-lAS-1 50-524-3 8.77, 8.78 1 6  : _ _

1. To centerline of SOV.

Table 4.8-9 IAS Line 5 Inboard Pipe Data Piping Leading Up To Inboard IV Starting Location: 21AS*V178 Stopping Location: 21AS*SOV184 Bends Horizontal Length Vertical Length 0 Pipe Segment 2-1AS-150-807-3 Note Reference 8.84,8.88 (deg) 45 Feet Inches Feet Inches 7 8 5/8 2-1AS-150-807-3 8.84, 8.88 45 8 1/2 2-IAS-1 50-807-3 1 8.84, 8.88 4 10 13/16

1. To center of SOV.

Table 4.8-10 IAS Line 5 Interstitial Pipe Data Interstitial Piping Between IVs Starting Location: 21AS*SOV184 Stopping Location: 21AS*SOV166 Bends Horizontal Length Vertical Length Pipe Segment. Note Reference (deg) Feet Inches Feet Inches 2-IAS-1 50-990-2 8.84, 8.88 90 2 9 1/2 2-1AS-150-990-2 8.84, 8.88 180 _ 4 9 :3/8 2-IAS-150-990-2 8.84, 8.88 1  :  :

2-IAS-1 50-897-2 1 8.84, 8.86 11  : 1/4 _

1. To center of SOV.

4.9. Nitrogen System (GSN) Line Table 4.9-1 GSN Line Interstitial Pipe Data Interstitial Piping Between lVs I Starting Location: 2GSN*V170 D:\Calc File\H21C-093 Rev 000.doc

NUCLEAR ENGINEERING CALCULATION CONTINUA Page 37l Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00

-let.

Stopping Location: 2GSN*SOV166 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-GSN-500-152-2 3 8.71, 8.73 4 i  !

2-GSN-500-152-2 8.71, 8.73 7 5  ;-i 2-GSN-500-152-2 1 8.71, 8.72 180 i 10  :

2-GSN-500-152-2 1 8.71,8.72 90 3 11 3/16 2-GSN-500-151-2 8.71, 8.72 90  ! 10 7/16 2-GSN-500-151-2 2 8.71, 8.72 4 ', 1/4  :

1.3/4" Flex hose

2. Inboard of SOV

3. Outboard of check valve.

4.10. 1" Primary Containment Purge (CPS) Lines Table 4.10-1 1" CPS Line 1 Interstitial Pipe Data Interstitial Piping Between lVs 0 Starting Location: Z-96 Penetration Stopping Location: 2CPS*SOV132 Bends Horizontal Length Vertical Length Pipe Segment Note Reference (deg) Feet Inches Feet Inches 2-CPS-001-41-2 8.60, 8.68 90 6 i 1/16 _

2-CPS-001-41-2 8.60, 8.68 90 4 2 2-CPS-001 2 8.60, 8.68 3 5/8 _

2-CPS-001-41-2 8.60, 8.68 8 2 9/16 " !_

2-CPS-001-41-2 8.60, 8.68 3 5 i i Table 4.10-2 1" CPS Line 2 Interstitial Pipe Data S Starting Location:

Stopping Location:

Interstitial Piping Between IVs Z92 Penetration 2CPS*SOV133 D:\Calc File\H21 C-093 Rev OOO.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 38 (Next 3) 0 Project: Nine Mile Point Nuclear Station Originator/Date Shane R. Gardner (CNS) / 5[7/04 Reviewer/Date Unit: 2 I Glenn Stinson / 7/30/04 Calculation No.

H21 C-093 Disposition: N/A Revision 00 Fief.r Bends Horizontal Length Vertical Lenqth Pine Seoment Note Reference Ideo) Feet Inches Feet Inches 2Pine 2-C S-001-45-2 PS-001-45-2 No0 8dFee.t 8.60, 8.65 1 90

___ ___ 1 2-CPS-001 2 8.60, 8.65 90 _ 4 6 2-CPS-001-45-2 8.60, 8.65 2 5 i i 2-CPS-001-45-2 8.60, 8.65 2 8 _ ,

4.11. Pipe Data for Bypass Lines Evaluated The following table provides a summary of piping class data for the piping systems evaluated in this calculation. This data was collected from a variety of sources. All the data except the pipe inside diameters were taken from the NMP MEL (Ref. 8.105). This confirms the nominal size of the pipe, the schedule and the quality classification. For the MSLs, the pipe inner diameter was taken from the

'Tabulation of Specific Pipe" listed in the NMP pipe specification (Ref. 8.106). This was due to the special pipe schedule. For the rest of the pipes, the inner diameter was taken from the Crane manual (Ref. 8.107).

0 Table 4.11-1 Bypass Line QA Classification and Size Data Summary NOM SIZE/

QUAL SEfS QA RATING PIPE PIPE SERVICE PIPE ID Pipe Line SAFETY GRP (SSE) CAT. (in.) CLASS SCHEDULE CODE (in.)

D:\Calc File\H21 C-093 Rev 000.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 39 (Next 0 Project:Nine Mile Point Nuclear Station Originator/Date Reviewer/Date Unit: 2-Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04_ H21C-093 00 Her.

NOM SIZE/

QUAL SEIS QA RATING PIPE PIPE SERVICE PIPE ID Pipe Line SAFETY GRP (SSE) CAT, (in.) CLASS SCHEDULE CODE (in.)

Inboard MSLs SR A I 1 26.00 901 SPW STM 23.481 Interstitial MSLs SR A I 1 26.00 901 SPW STM 23.481 Outboard MSLs 09 D I 1 28.00 901 SPW STM 25.23 MS Header Q9 D I 1 48.00 901 SPW STM 41 MSL Up To TSV 09 D I 1 28.00 901 SPW STM 25.23 2 in.

Inboard/Outboard SR A/B I 1 2.00 901/901C 160 STM 1.687 MSL Drain Lines 6 in. Inboard SR A 1 1 6.00 901 80 STM 5.761 MSL Drain Line 1 in. Outboard SR B 1 1 1.00 901 160 STM 0.815 MSL Drain Lines 3/4 in. Outboard SR B 1 1 0.75 901/901C 160 STM 0.612 MSL Drain Lines 1 1/2 in. IAS SR B/C I 1 1.50 602/302 40S/STD N2 1.61 Lines GSN Lines SR B I 1 0.50 153 STD N2 0.622 1 in. CPS Line to Suppression Pool SR B I 1 1.00 302 STD N2 1.049 SOVs 2in.CPSLinein SR B I 1 2.00 151 80 AIR 1.939 Drywell 14in.CPSLine SR B 1 1 14.00 151 STD AIR 13.25 in Drywell 2in.CPSLinein SR B I 1 2.00 153 STD AIR 2.067 Wetwell 12 in. CPS Line SR B I 1 12.00 151 STD AIR 12 in Wetwell 6 in. Drywell SR B I 1 6.00 153 STD WTR 6.085 Floor Drain Line 3 in. Drywell Floor Drain Tank SR B I 1 3.00 153 STD WTR 3.068 Vent Line 4 in. Drywell Equipment Drain SR B I 1 4.00 153 STD WTR 4.026 Line L D:\Calc FileNH21 C-093 Rev 0O0.doc:

0 ý 011

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 40 (Next -

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 lRef.1 NOM SIZE/

CUAL SEIS CA RATING PIPE PIPE SERVICE PIPE ID Pipe Line SAFETY GRP (SSE) CAT. (in.) CLASS SCHEDULE CODE (

2 in. Drywell Equipment Drain SR B I 1 2.00 153 STD AIR 2.067 Tank Vent Line 24 in. SCH 80 SR A I 1 24.00 901 80 WTR 21.562 Feedwater Lines 24 in. SCH 140 Feedn.terHn1s0 SR A I 1 24.00 1511 140 WTR 19.876 Feedwater Lines RWCU Lines SR107 NC I 1 8.00 901 80 WTR 7.625 PASS Lines SR B I 1 0.75 153 STD AIR 0.824

5. Calculations Using the raw data in Section 4, Excel spreadsheets were prepared to compute the piping line volumes and areas. The area determined in these evaluations is the total inside surface area of the piping system. The internal area of piping, which is oriented in a vertical position is computed separately from horizontally aligned piping. This is because aerosol deposition, which is a gravimetric process, would not occur on vertical pipe surfaces. The general equations which are used in the Excel spread sheets are:

Internal Area = 2 1T R L Internal Volume = L TT R2 R is the piping run internal radius and L length at that radius. The individual results of these computations are shown in Section 6 below, and summarized in Tables 6.11.

Figures 5-1 through 5-8 are provided as a visual aid to depict the piping considered for this analysis.

The pipelines indicated in bold, along with the QA CAT 1 boundaries, show the portion of the bypass lines that were analyzed. The data provided in Section 4 above corresponds directly to these figures.

D:\CaIc File\H21 C-093 Rev 000.doc

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Project: Nine Mile Point NuclearStation 0

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. Project: Nine Mile PointNuclear Station Originator/Date Reviewer/Date Unit: 2 Calculation No.

Disposition: N/A Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 Rief.

Figure 5-2 Schematic of Drywell Equipment Drain and Vent Bypass seismic I/

2-DER-002-34-2 -72.OER-02. 42 CA CAT 1 2DER*MOV130 2DER'MOV131 Various Drains 141 4.1 4.] I1l/-- 2-DER-OD4-17-2 2-DER-002-32-4 L.1L.2-DER-004- 4-2 -

2-DER.004-18-2 2DER*ov 19 2)ER*MOv120 2-DER-004-13-2 Inside Primary Containment 2-DER-O04-15-4 Drywall Equpment Drain Cooler 2DER-E1 Drywell Equipment Drain Tank 2DER-TK1 D:\Calc File\H21C-093 Rev OO0.doc

[NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 4 I ~~Next ___

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0 D:\CaIc File\H21C-093 Rev OOO.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 44 (Next Project: Nine Mile PointNuclear Station Unit: 22 Disposition: N/A Originator/Date Reviewer/Date ' Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 I: .IefI -- -

D:\CaIc File\H21C-093 Rev 0OO.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 45 (Next Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 Ref.1 Schematic of 2", 12" and 14" CPS Bypass D:\Calc File\H21C-093 Rev 000.doc

f NUCLEAR ENGINEERING I

CALCULATION CONTINUATION SHEET Page (Next 46_

Project: Nine Mile PointNuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7104 Glenn Stinson / 7/30/04 H21 C-093 00

[Ref.F D:\Calc File\H21C-093 Rev 000.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 47 (Next _)I Project:Nine Mile Point Nuclear Station Unit: 2- Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 Ref.

Figure 5-7 Schematic of PASS Bypass 2-CMS-750-42 2 CMS-750-51-2 CMS-750-69-2 2CMS*SOv24D 2CMS*SOV23F 2CMS'SOV23E 2CMS'SOV24C F'7" 2-CMS-50-79-2 2CM *S0V24B 2CMS*SOV23D 2CMS*SOV23C 2CMS*S 44A 2-CMS-750-77-2 2CMS'SOV74A 2CMS'SOV23B 2CMS*SOV23A

-- 2-CMS-750-79-2 t2CPMS'S0V74B 2-CMS-750-rTY-2 -

• 2 7Inside Primary Containment CMS-750-26-2 2-CMS-TSG-71-2 2-CMS-750-4-2 -M7522 2CMS*SOV7CB 2CMS'SOV'75A 2-CMS-75.04. 2-CMS-750-7622 2-CMS-750-834 . 114 114' .2-CMS-75081-4 PASS Sample Station IPNL101 D:\Calc File\H21C-093 Rev OO0.doc

NUCLEAR ENG)NEERING I CALCULATION CONTINUATION SHEET IPage -48 ). [~x Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date CalculationNo. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 STetf Figure 5-8 Schematic of Combined IAS/GNS/CPS Bypass Seismic II 2-GSN500-150-4QA CAT 1 2GSNWSOV~ 30.Inside Primary Co tainment 2GSN-159 (2GSN-V161

>-2.GSN-500-152 2-GSN-150-9-4 2GSN*VI70 2-GSN-500-1 80-4 314" Flax htose 2-GS 4I-500-151-2 Seismic II 2-GSN-025-5-4 QA CAT 1 2GSN-V53 2GSN-V55 2GSN-V58 2GSN-V54 2GSN-V56 2GSN-V59 Air Control~

2GSN-TK2 2-IAS-150-97.2- 2-IAS-150.990-2 LMca~m

-N L21AS*S0V184 2lAS'V1 2-IAS-150-565fl81-2-IAS-150-586,t761-4 2-IAS-150-7144 t21S'-C V 80 2IAS*VI81 0-117 0 2-IAS215AS-130771642S -

21AS*V182 Vacuum S-"eismic

/ I GA CAT 1 2IAS*SOV185 Ins. ank Ar Rceier 2-IS 24AS7-15 ,-2-IAS-150-525.2 2IAS-TK3 - 24IAS-150-524-2 21AS*SOVX181 21AS*SOV1 64 21AS*V448 2lAS*V179 2-IAS-150-755-3 2-lAS- 50-898-2 2CPS-0ei-41-2 2- 2-CPS-750-43-3 2-CPS-001-40 - Z - z 21AS*Th4 2CPS.SOV1 34 2CPS~V50 2CPS*V44 2CPS*SOV107 2-CPS-00F452 - -2CPS-750-46-3 2-CPS-001-44-4

-1L :PsoviM 2CPS*V51 2CPS*V49 2CPS'SOV109 Seismic I /

QA CAT 1 2A V52 K3A65421,AOSV F2AOSV8 2lAS*TK5 2-IAS-150-760-3 2IAS'SOVX186 2-IAS-150-837-2 2-AS-14-779 2-lSi5 ~ 2-IAS-150-756-3 21AS*SO V16 D;\Calc File\H21 C-093 Rev 000.doc I - - -1

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 49 (Next Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date ] Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 Ret.

6. Results I

This section summarizes the results of the Excel spreadsheets. Tables 6.11-1 through -3 provide an overall summary of the output data.

6.1. Main Steam Lines (MSL)

Table 6.1-1 Main Steam Line A Results Horiz. Horiz Vert. Vert.

Segment Area (f 2) Vol (fte) Area (ft2 ) Vol (ft3)

Reactor to Inboard IV 244.93 119.82 432.30 211.47 Interstitial Between IVs 121.41 59.39 0.00 0.00 Outboard IV to CAT 1 516.31 271.38 298.75 157.03 0

Table 6.1-2 Main Steam Line B Results Horiz. Horiz Vert. Vert.

3 2 Segment Area (ft) Vol (ft ) Area (ft ) Vol (ft3)

Reactor to Inboard IV 291.13 142.42 443.89 217.14 Interstitial Between IVs 133.80 65.45 0.00 0.00 Outboard IV to CAT 1 516.58 271.53 297.99 156.63 Table 6.1-3 Main Steam Line C Results Horiz. Horiz Vert. Vert.

Segment Area (fte) Vol (ft3) Area (ft2 ) Vol (ft3)

Reactor to Inboard IV 291.68 142.68 444.14 217.27 Interstitial Between IVs 134.28 65.69 0.00 0.00 Outboard IV to CAT 1 516.24 271.35 298.13 156.70 DA.Calc File\H21C-093 Rev O00.dac 0

[NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 50 ]

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Project: Nine Mile Point Nuclear Station Unit: 2- Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision S hane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00

-iet, Table 6.1-4 Main Steam Line D Results Horiz. Horiz Vert. Vert.

Segment Area (ft) Vol (f )3 Area (ft2) Vol (ft3)

Reactor to Inboard IV 245.28 119.99 433.00 211.82 Interstitial Between WVs 121.15 59.27 0.00 0.00 Outboard IVto CAT 1 516.17 271.31 297.65 156.45 6.2. Main Steam Drain Lines Table 6.2-1 Inboard Main Steam Line Drain Results Horiz. Horiz Vert. Vert.

0 Segment Reactor to Inboard IV Area (it )

28.28 2

Vol (Itf) 3.39 0.00 2

Area (It ) Vol (ift3) 0.00 Interstitial Between IVs 42.40 5.09 3.25 0.39 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 Table 6.2-2 Outboard Main Steam Line Drain Inboard Results Horiz. Horiz Vert. Vert.

Segment Area (Yf) Vol (ft3) Area (ft) Vol (ft3)

Reactor to Inboard IV 7.08 0.25 0.00 0.00 Interstitial Between lVs 0.00 0.00 0.00 0.00 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 D:\Calc FiIe\H21C-093 Rev 000.doc I - I

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-let.

6.3. Drywell Drains Table 6.3-1 Drywell Floor Drain Results Horiz. Horiz Vert. Vert.

Segment Area (ft2) Vol (ift3) Area (ft2 ) Vol (ft)

Reactor to Inboard IV 6.09 0.77 10.79 1.36 Interstitial Between IVs 13.41 1.69 0.00 0.00 Outboard IV to CAT 1 0.00 0.00 0.00 0.00 Table 6.3-2 Drywell Floor Drain Tank Vent Results Horiz. Horiz Vert. Vert.

Segment Area (ft12 Vol (ft3 ) Area (ft2) Vol (ft3)

Reactor to Inboard IV 0.00 0.00 0,00 0.00 Interstitial Between IVs 15.44 0.99 12.18 0.78 Outboard IV to CAT 1 0.00 0.00 0.00 0.00 Table 6.3-3 Drywell Equipment Drain Results Horiz. Horiz Vert. Vert.

Segment Area (ift) Vol (ft3) Area (ft2) Vol (fts)

Reactor to Inboard IV 27.39 2.30 13.24 1.11 Interstitial Between lVs 14.67 1.23 0.00 0.00 Outboard IV to CAT 1 0.00 0.00 0.00 0.00 D:\Calc File\H21 C-093 Rev OOO.doc

INUCLEAR EN .GINEERING CALCULATION CONTINUATION SHEET IPage(Nx 5_2 Project: Nine Mile Point NuclearStation Unit: 2- Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/0,4 H21 C-093 00

• ef.1 Table 6.3-4 Drywell Equipment Drain Tank Vent Results Horiz. Horiz Vert. Vert.

Segment Area (f12 ) Vol (ft) Area (f2 ) Vol (ft3)

Reactor to Inboard IV 0.93 0.04 0.00 0.00 Interstitial Between IVs 4.54 0.20 0.00 0.00 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 6.4. Feedwater Lines Table 6.4-1 Feedwater Line A Results Horiz. Horlz Vert. Vert.

0 Segment Reactor to Inboard IV Area (f 2 )

162.20 Vol (ftt) 71.95 Area (f 2) 170.04 Vol (ft3) 70.41 Interstitial Between IVs 72.01 29.82 0.00 0.00 Outboard IVto CAT 1 63.80 26.42 0.00 0.00 Table 6.4-2 Feedwater Line B Results Horiz. Horiz Vert. Vert.

Segment Area (112) Vol (if3) Area (ft2) Vol (ft3)

Reactor to Inboard IV 162.73 72.18 169.76 70.30 Interstitial Between IVs 71.90 29.77 0.00 0.00 Outboard IVto CAT 1 74.20 30.73 0.00 0.00 D:kCalc FleIeU-21 C-093 Rev 000.doc

NUCLEAR EGNRIGCALCULATION CONTINUATION SHEET Page 5 (INext

• Project: Nine Mile PointNuclear Station Unit: Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) /5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 R-et.

6.5. Primary Containment Purge (CPS) Lines in Drywell/Wetwell Table 6.5-1 2" CPS Line in Drywell Results Horiz. Horiz Vert. Vert.

3 Segment Area (W) Vol (ft ) 2 Area (Ift) Vol (ft3 )

Reactor to Inboard IV 0.51 0.02 0.00 0.00 Interstitial Between IVs 4.57 0.18 0.00 0.00 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 Table 6.5-2 14" CPS Line in Drywell Results Horiz. Horiz Vert. Vert.

0 Segment Reactor to Inboard IV Area (fte) 4.05 Vol (ft3) 1.12 Area (ft2) 0.00 Vol (ft3) 0.00 Interstitial Between IVs 40.40 11.15 0.00 0.00 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 Table 6.5-3 12" CPS Line in Wetwell Results D:\Calc File\H21 C-093 Rev QOOOdoc

N ULAREGIERIGCALCULATION CONTINUATION SHEET IPage 54

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• Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 1 Table 6.5-4 2" CPS Line in Wetwell Results Horiz. Horlz Vert. Vert.

Segment Area (f 2) Vol (ift) Area (fte) Vol (ft3)

Reactor to Inboard IV 0.97 0.04 0.00 0.00 Interstitial Between IVs 9.40 0.40 2.44 0.10 Outboard IV to CAT 1 0.00 0.00 0.00 0.00 6.6. Reactor Water Cleanup (RWCU) Line Table 6.6-1 RWCU Line Results Horlz. Horlz Vert. Vert.

Segment Area (Ift) Vol (ft 3) Area (ft2) Vol (ft3)

Reactor to Inboard IV 22.27 3.54 0.00 0.00 Interstitial Between IVs 26.28 4.18 0.00 0.00 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 6.7. Post Accident Sampling System (PASS) Lines Table 6.7-1 PASS Sample Line A Results Horiz. Horiz Vert. Vert.

Segment Area (ift) Vol (ft3) Area (ft2) Vol (ft3)

Reactor to Inboard IV 6.43 0.11 8.61 0.15 Interstitial Between IVs 0.22 0.00 0.00 0.00 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 D:\Calc File\21 C-093 Rev O00.doc;

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Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 Fief, Table 6.7-2 PASS Sample Line B Results Horiz. Horiz Vert. Vert.

Segment Area (ft) Vol (1f3) Area (ft) Vol (ft3)

Reactor to Inboard IV 18.29 0.31 11.91 0.20 Interstitial Between IVs 0.22 0.00 0.00 0.00 Outboard IV to CAT 1 0.00 0.00 0.00 0.00 Table 6.7-3 PASS Return Line A Results Horiz. Horiz Vert. Vert.

Segment Area (ft2) Vol (ft3) Area (ft2) Vol (fl3 )

Reactor to Inboard IV 14.28 0.25 10.33 0.18 0 Interstitial Between IVs 0.22 0.00 0,00 0.00 Outboard IV to CAT 1 0.00 0.00 0.00 0.00 Table 6.7-4 PASS Return Line B Results Horiz. Horlz Vert. Vert.

Segment Area (ft2) Vol (ft3) Area (Ift2) Vol (ft3)

Reactor to Inboard IV 7.65 0.13 5.53 0.09 Interstitial Between IVs 0.25 0.00 0.00 0.00 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 0

D:\Calc File\H21C.093 Rev OOO.doc

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av Project: Nine Mile PointNuclear Station Unit: ..2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 Iet.

6.8. Instrument Air (IAS) Lines Table 6.8-1 IAS Line 1 Results Horiz. Horiz Vert. Vert.

2 3 Segment Area ift ) Vol (ft ) Area (ift) Vol (ft3)

Reactor to Inboard IV 1.45 0.05 1.85 0.06 Interstitial Between IVs 1.98 0.07 1.21 0.04 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 Table 6.8-2 IAS Line 2 Results Horiz. Horiz Vert. Vert.

0 Segment Reactor to Inboard IV Area (ftl) 5.13 Vol (ft')

0.17 Area (ft 2) 2.42 Vol (ft3) 0.08 Interstitial Between lVs 1.15 0.04 1.22 0.04 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 Table 6.8-3 IAS Line 3 Results Horiz. Horiz Vert. Vert.

Segment Area (fte) Vol (ft3) Area (ft2) Vol (ft3)

Reactor to Inboard IV 3.50 0.12 1.12 0.04 Interstitial Between IVs 1.43 0.05 2.53 0.08 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 D:\Calc File\H21 C-093 Rev 000.doc

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Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date IReviewer/Date 1 Calculation No. Revision Shane R. Gardner (CNS) / 517/04 Glenn Stinson / 7/30/04 H21 C-093 00

-leT.

Table 6.8-4 IAS Line 4 Results Horiz. Horiz Vert. Vert.

Segment Area (ft2 ) Vol (ft 3) Area (ft2 ) Vol (ft)

Reactor to Inboard IV 1.19 0.04 0.00 0.00 Interstitial Between IVs 8.78 0.29 2.99 0.10 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 Table 6.8-5 lAS Line 5 Results Horiz. Horiz Vert. Vert.

Segment Area (ft2) Vol (f13) Area (hf 2) Vol (Wf3)

Reactor to Inboard IV 2.07 0.07 3.55 0.12 0 Interstitial Between IVs 1.99 0.07 2.02 0.07 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 6.9. Nitrogen System (GSN) Line Table 6.9-1 GSN Line Results Horiz. Horiz Vert. Vert.

Segment Area (ft2) Vol (ft3) Area (ft2) Vol (ft3)

Reactor to Inboard IV 0.00 0.00 0.00 0.00 Interstitial Between IVs 1.96 0.03 0.28 0.00 Outboard IVto CAT 1 0.00 0.00 0.00 0.00 DACaIc FiIe\H21C-093 Rev O0O.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 58

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I~x Project: Nine Mile Point NuclearStation Unit: 2- Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 Ref.

6.10. 1" Primary Containment Purge (CPS) Lines Table 6.10-1 1" CPS Line 1 Results Horiz. Horiz Vert. Vert.

Segment Area (ft1) Vol (ft3) Area (ft) Vol (ft3)

Reactor to Inboard IV 0.00 0.00 0.00 0.00 Interstitial Between IVs 4.17 0.09 1.14 0.03 Outboard IV to CAT 1 0.00 0.00 0.00 0.00 Table 6.10-2 1" CPS Line 2 Results Horiz. Horiz Vert. Vert.

Segment Area (ft2)' Vol (ft3) Area (ft2 ) Vol (ft3 )

Reactor to Inboard IV 0.00 0.00 0.00 0.00 Interstitial Between iVs 1.42 0.03 1.24 0.03 Outboard IV to CAT 1 0.00 0.00 0.00 0.00 D:\Calc File\H21 C-093 Rev 00O.doc

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 59 1 ~ ~(Next-0 Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date 1Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 4et.

1 6.11. Summary of Results Table 6.11-1 Summary of Pipe Data: Bends and Length Start to Inboard IV Interstitial Between IVs Outboard IV to CAT 1 Vertical Bends Horiz. Vertical Bends HorLz. Vertical Bends Horiz.

Pipe Segment (dg It) Mft Length (deg) Length Mdg Length Mit (deg) Length 00t fit Length Mdg (deg) Length MSL A 360.00 39.84 70.32 0.00 19.75 0.00 180.00 78.17 45.23 MSL B 405.00 47.36 72.21 0.00 21.77 0.00 180.00 78.21 45.11 MSL C 405.00 47.45 72.25 0.00 21.84 0.00 180.00 78.16 45.14 MSL D 360.00 39.90 70.44 0.00 19.71 0.00 180.00 78.15 45.06 MSL Inboard Drains 90.00 18.75 0.00 270.00 28.11 2.16 0.00 0.00 0.00 MSL Outboard Drains 90.00 16.04 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 Drywell Floor Drain 90.00 3.83 6.80 0.00 8.44 0.00 0.00 0.00 0.00 Drywall Floor Drain Tank Vent 0.00 0.00 0.00 368.00 19.22 15.17 0.00 0.00 0.00 Drywell Equip.

0 Drain Drywall Equip.

Drain Tank Vent 270.00 135.00 25.99 1.71 12.56 0.00 0.00 21.00 13.92 8.39 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Feedwater Line A 243.00 29.13 32.68 0.00 13.84 0.00 0.00 12.26 0.00 Feedwater Line B 243.00 29.22 32.63 0.00 13.82 0.00 0.00 14.26 0.00 2 in. CPS Line in Drywell 0.00 1.00 0.00 0.00 9.01 0.00 0.00 0.00 0.00 14 in. CPS Line in Drywall 0.00 1.17 0.00 0.00 11.65 0.00 0.00 0.00 0.00 12 in. CPS Line in Wetwell 90.00 4.72 6.76 0.00 10.96 0.00 0.00 0.00 0.00 2 in. CPS Line in Wetwell 0.00 1.79 0.00 360.00 17.38 4.50 0.00 0.00 0.00 RWCU 0.00 11.16 0.00 0.00 13.17 0.00 0.00 0.00 0.00 PASS Sample A 870.00 29.79 39.89 0.00 1.00 0.00 0.00 0.00 0.00 PASS Sample B 2262.00 84.78 55.21 0.00 1.00 0.00 0.00 0.00 0.00 PASS Return A 1284.00 66.21 47,89 0.00 1.00 0.00 0.00 0.00 0.00 PASS Return B 960.00 35.47 25.64 0.00 1.17 0.00 0.00 0.00 0.00 IAS Line 1 270.00 3.45 4.39 122.00 4.71 2.86 0.00 0.00 0.00 lAS Line 2 525.00 12.16 5.75 225.00 2.72 2.89 0.00 0.00 0.00

]AS Line 3 180.00 8.30 2.67 270.00 3.39 6.01 0.00 0.00 0.00 IAS Line 4 0.00 2.82 0.00 360.00 20.83 7.10 0.00 0.00 0.00 lAS Line 5 90.00 4.90 8.43 270.00 4.73 4.78 0.00 0.00 0.00 GSN 0.00 0.00 0.00 360.00 12.04 1.70 0.00 0.00 0.00 1 in. CPS Line 1 0.00 0.00 0.00 180.00 15.19 4.17 0.00 0.00 0.00 1 in. CPS Line 2 0.00 0.00 0.00 180.00 5.17 4.50 0.00 0.00 0.00 D:\Cafc File\H21C-093 Rev 000.doc

NUCLEAR ENGINEERING Page 60 CALCULATION CONTINUATION SHEET tN~xt L \ I Project Nine Mile PointNuclearStation Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/0,4 H21C-093 00

let, Table 6.11-2 Summary of Results

Internal Areas Start to Inboard IV Interstitial Between IVs Outboard IVto CAT 1 Horizontal Vertical Horizontal Vertical Horizontal Vertical 2

Pipe Segment Area (tt) Area (11) Area (Wt) Area (fte) Area (ft) Area (ft)

MSL A 244.93 432.30 121.41 0.00 516.31 298.75 MSL B 291.13 443.89 133.80 0.00 516.58 297.99 MSL C 291.68 444.14 134.28 0.00 516.24 298.13 MSL D 245.28 433.00 121.15 0.00 516.17 297.65 MSL Inboard Drains 28.28 0.00 42.40 3.25 0.00 0.00 MSL Outboard Drains 7.08 0.00 0.00 0.00 0.00 0.00 Drowell Floor Drain 6.09 10.79 13.41 0.00 0.00 0.00 Drywell Floor Drain Tank Vent 0.00 0.00 15.44 12.18 0.00 0.00 Drywall Equip. Drain 27.39 13.24 14.67 0.00 0.00 0.00 Drywell Equip. Drain Tank Vent 0.93 0.00 4.54 0.00 0.00 0.00 Feedwater Line A 162.20 170.04 72.01. 0.00 63.80 0.00 Feedwater Line B 162.73 169.76 71.90 0.00 74.20 0.00 2 in. CPS Line in Drywell 0.51 0.00 4.57 0.00 0.00 0.00 14 in. CPS Line in Drywell 4.05 0.00 40.40 0.00 0.00 0.00 12 in. CPS Line in Wetwell 14.82 21.24 34.43 0.00 0.00 0.00 2 in. CPS Line in Wetwell 0.97 0.00 9.40 2.44 0.00 0.00 RWCU 22.27 0.00 26.28 0.00 0.00 0.00 PASS Sample A 6.43 8.61 0.22 0.00 0.00 0.00 PASS Sample B 18.29 11.91 0.22 0.00 0.00 0.00 PASS Return A 14.28 10.33 0.22 0.00 0.00 0.00 PASS Return B 7.65 5.53 0.25 0.00 0.00 0.00 IAS Line 1 1.45 1.85 1.98 1.21 0.00 0.00 IAS Line 2 5.13 2.42 1.15 1.22 0.00 0.00 IAS Line 3 3.50 1.12 1.43 2.53 0.00 0.00 IAS Line 4 1.19 0.00 8.78 2.99 0.00 0.00 IAS Line 5 2.07 3.55 1.99 2.02 0.00 0.00 GSN 0.00 0.00 1.96 0.28 0.00 0.00 1 in. CPS Line 1 0.00 0.00 4.17 1.14 0.00 0.00 1 in. CPS Line 2 0.00 0.00 1.42 1.24 0.00 0.00 D:\Calc File\H21 C-093 Rev 000.doc

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0 Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date I Reviewer/Date I Calculation No. IRevision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00

-et.

Table 6.11-3: Summary of Results: Internal Volumes Start to Inboard IV Interstitial Between IVs Outboard IV to CAT 1 Horizontal Vertical Horizontal Vertical Horizontal Vertical Pipe Segment Vol. (ftW) Vol. (ft) voi. (ft) Vol. (It) Vol. (fr) Vol. (ft)

MSL A 119.82 211.47 59.39 0.00 271.38 157.03 MSL B 142.42 217.14 65.45 0.00 271.53 156.63 MSL C 142.68 217.27 65.69 0.00 271.35 156.70 MSL D 119.99 211.82 59.27 0.00 271.31 156.45

.MSL Inboard Drains 3.39 0.00 5.09 0.39 0.00 0.00 MSL Outboard Drains 0.25 0.00 0.00 0.00 0.00 0.00 Drywell Floor Drain 0.77 1.36 1.69 0.00 0.00 0.00 Drywell Floor Drain Tank Vent 0.00 0.00 0.99 0.78 0.00 0.00 Drywell Equip. Drain 2.30 1.11 1.23 0.00 0.00 0.00 Drywell Equip. Drain Tank Vent 0.04 0.00 0.20 0.00 0.00 0.00 Feedwater Line A 71.95 70.41 29.82 0.00 26.42 0.00 Feedwater Line B 72.18 70.30 29.77 0.00 30.73 0.00 2 in. CPS Line in Drywell 0.02 0.00 0.18 0.00 0.00 0.00 14 in. CPS Line in Drywell 1.12 0.00 11.15 0.00 0.00 0.00 12 in. CPS Une in Wetwell 3.71 5.31 8.61 0.00 0.00 0.00 2 in. CPS Line In Wetwell 0.04 0.00 0.40 0.10 0.00 0.00 RWCU 3.54 0.00 4.18 0.00 0.00 0.00 PASS Sample A 0.11 0.15 0.00 0.00 0.00 0.00 PASS Sample B 0.31 0.20 0.00 0.00 0.00 0.00 PASS Return A 0.25 0.18 0.00 0.00 0.00 0.00 PASS Return B 0.13 0.09 0.00 0.00 0.00 0.00 IAS Line 1 0.05 0.06 0.07 0.04 0.00 0.00 IAS Line 2 0.17 0.08 0.04 0.04 0.00 0.00 IAS Line 3 0.12 0.04 0.05 0.08 0.00 0.00 IAS Line 4 0.04 0.00 0.29 0.10 0.00 0.00

[AS Line 5 0.07 0.12 0.07 0.07 0.00 0.00 GSN 0.00 0.00 0.03 0.00 0.00 0.00 1 in. CPS Line 1 0.00 0.00 0.09 0.03 0.00 0.00 1 in. CPS Line 2 0.00 0.00 0.03 0.03 0.00 0.00 D:\Calc FileXH21 C-093 Rev O00.doc 0 01111111111111111!

NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 62 j (Next - )

. Project: Nine Mile Point Nuclear Station Shane R. Gardner (CNS) / 5/7/04 Unit: 2 Glenn Stinson / 7/30/04 H21C-093 Disposition: N/A 00 et.

7. Conclusions The above calculation provides physical parameters for use in the evaluation of bypass leakage pathways for NMP U2. The data is summarized in its entirety in Tables 6.11-1 through -3.

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NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 63 (Next

• Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21 C-093 00 ef.

8. References 8.1. Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," USNRC, July 2000.

8.2. AEB-98-03, "Assessment of Radiological Consequences for the Perry Pilot Plant Application using the Revised (NUREG-1 465) Source Term, USNRC, December 8, 1998.

8.3. NMP Calculation PR-C-28-E-02C, 6-26-98, "Design Basis Loss of Coolant Accident Doses in the Control Room and at the EAB and the LPZ from All Sources Based on a 60 Minute Drawdown Time and Leakage of 24 scfh per MSIV."

8.4. Calculation ES-1 77-05, 10/22/86, "Secondary Containment Bypass Leakage", including:

a. Supplement 05-SPL-1, 11/22/88,

b. Supplement 05-SPL-2, 5/9/89,

c. Disposition ES-1 77-05A, 9/21/94,

d. Disposition ES-177-05B, 12/8/94,

e. Disposition ES-1 77-05C, 12/8/94

f. Disposition ES-1 77-05D, 3/7/95 and

g. Disposition ES-177-05E, 7/23/96.

8.5. Nine Mile Point Nuclear Station Unit 2 Updated Safety Analysis Report (UFSAR), Rev. 15, October 2002 8.6. NMP Unit 2 Technical Specifications.

8.7. NUREG/CR-6604, "RADTRAD: A Simplified Model for Radionuclide Transport and Removal And Dose Estimation," April 1998.

8.10. Drawing PID-001-02, SH1, "P&ID Main Steam Fundamental."

8.11. Drawing PID-001A-06, "P&ID Main Steam."

8.12. Vender Drawing 2MSS-001 -013, "As-Built Drawing AX-2A", SWEC File No. 6.221-819-005E and/or "As-Built Drawing AX-2E", SWEC File No. 6.225-819-001 B 8.13. Drawing PID-001B-07, "P&ID Main Steam."

8.14. Vender Drawing 2MSS-001 -014, "As-Built Drawing AX-2B", SWEC File No. 6.222-819-006D and/or "As-Built Drawing AX-2E", SWEC File No. 6.225-819-002B 8.15. Drawing PID-001C-06, "P&ID Main Steam."

8.16. Vender Drawing 2MSS-001 -015, "As-Built Drawing AX-2C", SWEC File No. 6.223-819-006C and/or "As-Built Drawing AX-2E", SWEC File No. 6.225-819-003B.

8.17. Drawing PID-001 D-05, "P&ID Main Steam."

DACalc File\H21C-093 Rev OOO.doc

NUCLEAR ENGINEERING CALCULATION CONTINUAT SHEET P age Nx 64'

_I Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane R. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 Ref. 8.18. Vender Drawing 2MSS-001-016, "As-Built Drawing AX-2D", SWEC File No. 6.224-819-004D and/or "As-Built Drawing AX-2E", SWEC File No. 6.225-819-004B.

8.19. Drawing PID-O01J-06, "P&ID Main Steam."

8.20. Drawing PID-001 E-15, "P&ID Main Steam."

8.21. Vender Drawing Iso No. 01-17 Rev. M,"MSS Piping", SWEC File No. 5.110-065-056D.

8.22. Vender Drawing Iso No. 01- 19 Rev E, "MSS Piping", SWEC File No. 5.110-065-078C.

8.23. Drawing DP-302B-05, "Isometric Drawing - Reactor Building Main Steam Piping (2MSS)

Primary Containment Elevation 240'-9".

8.24. Vender Drawing Iso No. 01-21 Rev K,"MSS Piping", SWEC File No. 5.110-065-080C.

8.25. Vender Drawing Iso No. 01-20 Rev N, "MSS Piping", SWEC File No. 5.110-065-079C.

8.26. Vender Drawing Iso No.01-018 Rev H, "MSS Large Bore Piping", SWEC File No. 5.110-065-076E.

8.27. Drawing EP-1 39A-06, "Main Steam Drain Piping" 8.28. Drawing PID-001F-18, "P&ID Main Steam."

8.29. Drawing DP-302R-10, "ISO DWG Reactor Bldg. Main Steam Piping (2MSS) Sec. Contmt El 240'-0".

8.30. Drawing PID-001G-16, "P&ID Main Steam."

8.31. Vender Drawing 2MSS-001 -004, "As-Built Drawing AX-2E", SWEC File No. 6.225-819-005B.

8.32. Vender Drawing Iso No. 01-05 Rev M,"MSS Piping", SWEC File No. 5.110-065-01 OF.

8.33. Drawing PID-037-02, SH1, "P&ID Reactor Water Cleanup System Fundamental."

8.34. Drawing PID-037A-1 8, "P&ID Reactor Water Cleanup System."

8.35. Vender Drawing Iso. No. 09-05 Rev Z, '"CS Piping", SWEC File No. 5.190-065-419D.

8.36. Drawing DP-374AJ-04, "ISO DWG Reactor BLDG. Reactor WTR Cleanup PP (2WCS) PRI CONTMT EL. 261 '-0"

• 8.37. Vender Drawing 2WCS-009-06, Rev. AN, "WCS Piping", SWEC File No. 5.190-065-420D.

8.38. Vender Drawing 2WCS-009-07, Rev. Y,"WCS Piping", SWEC File No. 5.190-065-421G.

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I NUCEAR J CALCULATION CONTINUATION SHEET I ~(Next

• Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: N/A Originator/Date Reviewer/Date Calculation No. Revision Shane Ft. Gardner (CNS) / 5/7/04 Glenn Stinson / 7/30/04 H21C-093 00 Ref.

8.39. Drawing PID-006-01, SH1, "P&ID Feedwater System Fundamental" 8.40. Drawing PID-006B-24, "P&ID Feedwater System."

8.41. Vender Drawing Iso. No.47-008 Rev M, "FWS System Large Bore Piping", SWEC File No.

5.120-065-074E.

8.42. Drawing 2FWS-47-013, Rev. 13, "Final As-Built Dwg AX-17B", SWEC File No. 6.122-819-001C.

8.43. Vender Drawing Iso. No.47-014 Rev M, "FWS Piping", SWEC File No. 5.120-065-081 D.

8.44. Vender Drawing Iso. No.47-009 Rev 0, "FWS System Large Bore Piping", SWEC File No.

5.120-065-075E.

8.45. Vender Drawing 47-016, Rev. 17, "Final As-Built Dwg AX-1 7A", SWEC File No. 6.121-819-001C.

8.46. Vender Drawing Iso. No. 47-17 Rev N, "FWS Piping", SWEC File No. 5.120-065-084D.

8.47. Drawing PID-067A-17, "P&ID Drywell Equipment Drains."

8.48. Drawing DP-385B-05, "ISO DWG REACTOR BLDG NUCLEAR EQUIPT. VENT & DRAIN PP.

(2DER) PRI. CONTMT. EL. 240'-9" 8.49. Drawing DP-385AW-06, "ISO. DWG. REACTOR BLDG. NUC. EQPT. VENT & DRAIN PP (2DER) SEC. CONTMT. EL. 175'-0" 8.50. Drawing DP-385AX-04, "ISO DWG-REACTOR BLDG NR EQUIPMENT VENT & DRAIN (2DER) SEC CONTMT EL 175'-0" 8.51. Vender Drawing Iso. No. 28-1F Rev L, "DER Piping", SWEC File No. 5.190-065-336E.

8.52. Vender Drawing Iso. No. 28-2F Rev K, "DER Piping", SWEC File No. 5.190-065-337E.

8.53. Vender Drawing Iso. No. 28-3F Rev Q, "DER Piping", SWEC File No. 5.190-065-338F.

8.54. Drawing PID-063E-1 6, "P&ID Reactor Building Equipment and Floor Drains."

8.55. Drawing PID-063C-1 6, "P&ID Reactor Building Equipment and Floor Drains."

8.56. Vender Drawing Iso. No. 31-09 RevW, "R.B.FLR. & Equip. Drains", SWEC File No. 5.190 353F.

8.57. Vender Drawing 31-009, Rev. 10, "As-Built Drawing of AX-85A", SWEC File No. 6.061-819-001C.

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8.58. Vender Drawing Iso. No. 31-5F Rev AD, "DFR Piping", SWEC File No. 5.190-065-335G.

8.59. Vender Drawing ITT Grinnel Ind. Piping Inc. Iso. No. 31-6F Rev D,"Drain From 240'-0" to Drywell Floor Drain Tank.

8.60. Drawing PID-061 A-1 2, "P&ID Primary Containment Purge &Standby Gas Treatment."

8.61. Drawing DB-31 5F-09, "ISO DWG REACTOR BLDG AIR COOL AND PURGE PP (2CPS)

SEC CONTMT EL 289'-0" 8.62. Vender Drawing 24-002. Rev. 11, "As-Built Drawing of AX-515E", SWEC File NO. 6.524-819-001B.

8.63. Vender Drawing 24-001. Rev. 24, "As-Built Drawing of AX-515A", SWEC File NO. 6.521-819-001D.

8.64. Drawing DB-315A-12, "ISO. DWG. REACTOR BLDG. AIR COOL AND PURGE PP. (2CPS)

PRIM. & SEC. CONTMT. EL. 215'-0" O 8.65. Drawing DB-315J-03, "ISO DWG. REACTOR BLDG. AIR COOL AND PURGE PP (2CPS)

SEC CONTMT EL 215'-0" 8.66. Drawing DB-315K-02, "ISO DWG. REACTOR BLDG. AIR COOL AND PURGE PP (2CPS)

SEC CONTMT EL 215'-0" 8.67. Drawing DB-315H-02, "ISO DWG. REACTOR BLDG. AIR COOL AND PURGE PP (2CPS)

SEC CONTMT EL 215'-0" 8.68. Drawing DB-315L-03, "ISO DWG. REACTOR BLDG. AIR COOL AND PURGE PP (2CPS)

SEC CONTMT EL 216'-0" 8.69. Drawing DB-315N-05, "ISO DWG REACTOR BLDG AIR COOL AND PURGE PP (2CPS) PRI CONTMT EL 222'-6" 8.70. Drawing DB-315M-07, "ISOMETRIC DRAWING REACTOR BUILDING AIR COOL &

PURGE PIPING 2CPS PRIMARY CONTAINMENT ELEVATION 222 FEET - 6 INCH" 8.71. Drawing PID-105B-20, "P&ID Nitrogen System."

8.72. Drawing DP-453W-05, "ISOMETRIC DRAWING REACTOR BUILDING NITROGEN SYSTEM PP. (GSN) SEC. CONTAINMENT EL. 250'-0" 8.73. Drawing DP-453X-4, "ISO DWG REACTOR BLDG NITROGEN SYSTEM PP. (2-GSN)

PRIMARY CONTMT. EL. 247' -6" 8.74. Drawing PID-019F-15, "P&ID Instrument &Service Air."

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8.75. Drawing DP-340QR-06, "ISO DRAWING REACTOR BUILDING INTRUMENT AIR PIPING (21AS) SECONDARY CONTAINMENT EL. 289'-0" 8.76. Drawing DP-3400L-7, "ISO DRAWING REACTOR BUILDING INSTRUMENT AIR (21AS)

PRIMARY CONTAINMENT EL. 288' 3" 8.77.. Drawing PID-019G-25, "P&ID Instrument & Service Air."

8.78. Drawing DP-340JR-06, "ISO DWG REACTOR BLDG INSTRUMENT AIR PIPING (21AS) SEC CONTMT EL. 240' 0" 8.79. Drawing DP-340SA-06, "ISO DWG REACTOR BLDG INSTRUMENT AIR PIPING (21AS) SEC CONTMT EL. 289'-0" 8.80. Drawing DP-340JW-5, "ISO DWG REACTOR BLDG INSTRUMENT AIR PIPING (21AS) PRI CONTMT EL. 288'-3" 8.81. Drawing DP-340JX-10, "ISO DWG REACTOR BLDG INSTRUMENT AIR PIPING (21AS) PRI CONTMT EL. 305' -9" O 8.82. Drawing DP-340JV-6, "ISO. DWG. REACTOR BLDG. INSTRUMENT AIR P.P. (21AS) PRI.

CONTMT. EL. 288' -3" 8.83. Drawing DP-340V-6, "ISO DWG. REACTOR BUILDING INSTRUMENT AIR PIPING (21AS)

PRIMARY CONTAINMENT EL. 240' -9" 8.84. Drawing PID-01 9D-20, "P&ID Instrument & Service Air."

8.85. Drawing DP-340SF-07, "ISO DWG REACTOR BLDG INSTRUMENT AIR PIPING (21AS) SEC CONTMT EL. 289'-0" 8.86. Drawing DP-340SD-07, "ISO DWG REACTOR BLDG INSTRUMENT AIR PIPING (21AS)

SEC. CONTMT. EL. 289'-0" 8.87. Drawing DP-340QW-5, "ISO DRAWING REACTOR BUILDING INSTRUMENT AIR PIPING (21AS) PRIMARY CONTAINMENT EL. 288'-3" 8.88. Drawing DP-3400M-8, "ISO DRAWING, REACTOR BUILDING INSTRUMENT AIR PIPING (21AS) PRIMARY CONTAINMENT EL. 288' -3" 8.89. Drawing PID-082A-1 6, "P&ID Containment Atmosphere Monitoring System."

8.90. Drawing PID-106A-13, "P&ID Post Accident Sampling."

@ 8.91. Drawing DP-384BF-1 3, "ISO DWG REACTOR BLDG CONTMT ATM MONTG PP (2CMS)

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8.92. Drawing DP-384AG-09, "ISO DWG REACTOR BLDG CONTMT ATM MONTG PP (2CMS)

SEC. CONTMT. EL. 240'-0" 8.93. Drawing DP-384BW-07, "ISO DWG REACTOR BLDG CONTMT. ATM. MONT. SYS. (2CSM)

SEC CONTMT EL. 289'-0" 8.94. Drawing DP-384AU-07, "ISO DWG REACTOR BLDG CONTMT ATM MONTG PP (2CMS)

SEC. CONTMT. EL. 261 '-0" 8.95. Drawing DP-384AF-09, "ISO DWG REACTOR BLDG CONTMT ATM MONTG PP (2CMS)

SEC. CONTMT. EL. 240'-0" 8.96. Drawing DP-384AR-1 1, "ISO DWG REACTOR BLDG CONTMT ATM MONTG (2CMS) AUX.

BAY SOUTH EL. 240'-0" 8.97. Drawing DP-384AM-13, "ISO DWG REACTOR BLDG CONTMT ATM MONTG PP (2CMS)

SEC. CONTMT. EL. 261'-0" 8.98. Drawing DP-384AJ-10, "ISO DWG REACTOR BLDG CONTMT ATM MONTG PP (2CMS)

SEC. CONTMT. EL. 240'-0" 8.99. Drawing DP-384B-10, "ISO. DWG. REACTOR BLDG. CONTMT. ATM. MONTG. (2CMS)

AUX. BAY NORTH EL. 240'-0" 8.100'. Drawing DP-384AK-08, "ISO DWG REACTOR BLDG CONTMT ATM MONTG PP (2CMS)

SEC. CONTMT. EL. 240'-0" 8.101. Drawing DP-384AN-09, "ISO DWG REACTOR BLDG CONTMT ATM MONTG PP (2CMS)

SEC. CONTMT. EL. 261'-0" 8.102. Drawing DP-384AE-06, "ISO DWG REACTOR BLDG CONTMT ATM MONTG PP (2CMS)

SEC. CONTMT. EL. 240'-0" 8.103. Drawing EK-431J-02, "Sample Piping Reactor Building Part Plan EL 240'-0" 8.104. Drawing EK-32D-01, "Sample Piping Radwaste Tunnel & Sample Room Part Plan EL 244'-0"

&261'-0" 8.105. Nine Mile Point Unit 2 Master Equipment List (MEL) 8.106. NMP2-P301A, "Specification for Piping Engineering and Design, ASME III, Code Class 1,2, and 3 and ANSI B31.1," Nine Mile Point Nuclear Station Unit 2, Revision 2, November 24, 1986.

@ 8.107. Crane Engineering Data Catalog, Copyright 1976.

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=ef.

9. Appendices This appendix provides a listing of Excel Spreadsheets on CD-ROM.

Figure 9-1 Directory Listing of Excel Spreadsheets DATE TIME BYTES FILE NAME 08/02/2004 03 :04 PM 77,312 :12 Inch CPS Line in Wetwell.xls 08/02/2004 03 :00 PM 76,800 14 Inch CPS Line in Drywell.xls 03/25/2004 11:42 AM 76, 800 2 Inch CPS Line in Drywell.xls 03/25/2004 11:43 AM 76, 800 2 Inch CPS Line in Wetwell.xls 03/25/2004 11:44 AM 77,312 Drywell Equip Drain Lines.xls 03/25/2004 11:44 AM 76,800 Drywell Equip Tank Vent Line.xls

.08/02/2004 02 :59 PM 77,312 Drywell Floor Drain Line..xls 03/25/2004 11:45 AM 77,824 Drywell Floor Tank Vent Line.xls 03/25/2004 11:45 AM 142,848 Feedwater Lines.xls 08/04/2004 04:11 PM 510, 464 IAS-GSN-CPS Lines.xls 08/02/2004 02:57 PM 138,752 Main Steam Drain Lines.xls 05/04/2004 04:04 PM 276, 480 Main Steam Lines.xls 08/04/2004 03:24 PM 94,720 NMP2 Bypass Piping Analysis Summary.xls 0 08/02/2004 03/25/2004 08/03/2004 03:11 12 :03 02:39 PM PM PM 268,288 19, 968 76,800 PASS Lines.xls Pipe Data.xls RWCU Line.xls D:\Calc FileNH21C-093 Rev 000.doc