Text

Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures
	ML20217H581
Person / Time
Site:	Mcguire, McGuire
Issue date:	10/15/1999
From:	Barron H; DUKE POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20217H584	List: ML20217H581;
References
	NUDOCS 9910220163
	Download: ML20217H581 (47)
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s f] Duke Energy Cirpo.itlin 4( -

) " McGuire Nuclear Station 12700 Hagen Ferr- Road 4 Huntersville. NC 28078-9340 I 's -

(704) 875-4800 omCE

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. October 15,1999 U. S. Nuclear Regulatory Commission Attention: Document Control Desk-

' Wcshington, DC 20555

Subject:

~ McGuire Nuclear Station Docket Nos. 50-369 and 50-370 1999 Updated Final Safety Analysis Report

. Pursuant to 10 CFR 50.4, attached are the signed original and 10 copies of the McGuire Updated Final Safety Analysis Report (UFSAR). This update is provided as required by 10 CFR 50.71(e).

~

The effective date for this update is April 15,1999, as indicated in the lower margin of each replacement page. The changes are denoted with a change indicator "8" in the left mx;in' adjacent to the changes. The package includes update insertion instructions, list of effective pages for tables, list of effective pages for figures, Chapters 1 through 17 entire text, and revised tables and figures.

Please contact P.T. Vu at (704) 875-4302 for any quotions regaroing this subm'ttal. .

Very truly yours, H. B. Barron Attachments i

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PDR ADOCK 05000369" K PDR-

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l Octob'e r 15,1999

- Page 2l xc:

LA. Reyes

- Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900

' F. Rinaldi Senior Project Manager Office of U.S. Nuclear Regulatory Commission One White Flint North,~ Mail Stop 14E21 Washington,DC 20555 S.M. Shaeffer NRC Senior Resident Inspector McGuire Nuclear Station O

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V October 15,1999

. Page 3 H. B. Barron, being duly sworn, states that he is Vice President of McGuire Nuclear l Station; that he is authorized en the part of Duke Energy Corporation to sign and file with I the U.S. Nuclear Regulatory Commission this revision to the McGuire Nuclear Station l

Final Safety Analysis Report; and that the'information accurately presents changes made

..since the previous submittal, necessary to reflect information and analyses submitted to the Commission or prepared pursuant to Commission requirements, and changes made

- under the provisions of 10 CFR 50.59 but not previously submitted to the Commission.

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H. B. Barron, Vice President '

Subscribed and swom to before me this 15th day of October 1999, i

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Notary Public Deborat, G. Thesy .

My Commission Expires:

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Recipients in McGuire Document Control distribution code MADM-01 listing ELL (EC050) l l

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! f% MNS UFSAR 1999 UPDATE l

J INSERTION INSTRUCTIONS Submittal Date: 10/15/99 f Effective Date: 4/15/99

1. Replace entire text portions ( including the Table of Contents, List of Figures, and List of Tables) for each l chapter with the updated text portion.

l I

2. For Tables and Figures, update according to the following instructions (NOTE: The revised 11 x 17 inch drawings are bundled separately from the revised text, tables and 8.5 x 11 inch drawings. The revised 8.5 x 11 inch drawings are included with the revised text and tables which are bundled in chapter order. The revised drawings that are denoted with "*" are 8.5 x 11 inch drawings; otherwise, they are 11 x 17 inch drawings.) ;

Remove Insert l Entire List of Effective Dates for Entire List of Effective Pages for Table Pages,1999 Interim Update Tables,1999 Update Entire List of Effective Dates for Entire List of Effective Pages for

- Figure Pages,1999 Interim Update Figures,1999 Update Chapter 1 Table 1-5 Table 15

, Table 1-7 Figure 1-7 Figure 1-7 Figure 1 17 p

.I Chapter 3 Table 3-18 Table 3-18 Chapter 5 Table 5-5 Table 5-5 Table 5-15 Table 5-15 Table 5-17 Table 5-17 Table 5-33 Table 5-33 Chapter 6 Tables 6-13,6-14, & 6-15 Table 6-13,614 & 6-15 Tables 6-18 (p.3) & 6-19 Table 6-18 (p.3) & 6-19 Tables 6-46,6-47,6-48 & 6-49 Table 6-46,6-47,6-48, & 6-49 Tables 6-94 Table 6-94 Tables 6-107 Tables 6-108 Table 6-108 Tables 6-109 Table 6-109 '

Tables 6-110 (p. 2 to 5) Table 6-110 (p. 2 to 5)

. Tables 6-111 Table 6-111 l Tables 6-112 Table 6-112

, Tables 6-113 Table 6-113 l

Tables 6-114 Table 6-114 Tables 6-116 Table 6-116 Tables 6-117 Table 6-117 Tables 6-123 Table 6-123 p Tables 6-125 (p. 2) Table 6-125 (p.2)

(-) Tables 6-126 Tables 6-127 Table 6-126 Table 6-1-27 1999 Update l

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N Tables 6-131 Table 6-131 I ) ' Tables 6-132 Table 6-132

-D. Tables 6-133 Table 6-133

.. Tables 6134. Table 6-134 Tables 6-135 .

Table 6-135 Tables 6-138 ~ Table 6-138 Tables 6-139 Tabie 6-139

. Tables 6-140 Table 6-140 '

Tables 6-141 Table 6-141 y

Figure 6-1 (p. 2) - . Figure 6-1 (p. 2)

Figure 6-3 Figure 6-3 Figure 6-8 Figure 6-8

Figure 6-9 Figure 6-9

Figure 6-10 Figure 6-10

Figure 6-11 Figure 6-11

Figure 6124 Figure 6-124

Figure 6-182 Figure 6-182 Figure 6-184 Figure 6-184 Figure 6-196 Figure 6-196

Chapter 7 Table 7-1 (p.1) Table 7-1 (p.1)

Table 7 Table 7-2 Table 7-4 Table 7-4 Table 7-5 Table 7-5 Table 7-6 Table 7-6

O Table 7-7 Table 7-8 Table 7-7 Table 7-8 Table 7-12 Table 7-12 Table 7-13 Table 713 Table 714 Table 714 Table 7-16 Table 7-16 Table 7-17 Table 717 Table 7-18 Table 7-18 i Table 7-19 Table 7-19 Figure 71 (p. 7 & 8) Figure 7-1 (p. 7 & 8)

Figure 7-2 Figure 7-2

Figure 715 Figure 7-15

Figure 719 Figure 719 * .

Figure 7-26 Figure 7 26

l Figure 7 30 Figure 7-30

Figure 7-31 Figure 7-31

Chapter 8 Table 8-1 (p. 5 to 9) Table 8-1 (p. 5 to 10) j Table 8-5 Table 8-6 Table 8-6 Table 8-7 (p. I to 3) Table 8-7 (p. I to 3)

Table 8-8 Table 8-8 Table 8-11 Table 811 Table 813 (p. 2) Table 8-13 (p. 2)

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1999 Update i l

g Figure 8-1: ~ Figure 8-1 Figure 8-2 Figure 8-2

'- Figure 8-5 Figure 8 '

l Figure 8-7 Figure 8 Figure 8-8 Figure 8-8 l Figure 8-13 Figure 8-13 Figure 8-16 ' .

Figure 8-16 Figure 8-17 (p.1 & 2) Figure 8-17 (p.1 & 2) i Figure 8 Figure 8-18 Figure 819 Figure 8-19 !

Figure 8-21 .)

Figure 8-22 ,

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Figure 8 23 Figure 8-24 Figure.8-25 Figure 8-26 Figure 8-27

. Figure 8-28 Figure 8-28 Figure 8-31 Figure 8-31

Figure 8-34 Figure 8-34 i

Chapter 9 Figure 9-13 Figure 9-13 i Figure 9-30 Figure 9-30 Figure 9-54 Figure 9-54 Figure 9-56 Figure 9-56 Figure 9-74 Figure 9-74

.O ' Figure 9-79 :

Figure 9-119 (p.1)

Figure 9-79 Figure 9-119 (p.1) ~l Figure 9-143 Figure 9-143 i Figure 9-150 Figure 9-150 Chapter 10 Figure 10-1 Figure 10-1 Figure 10-2 Figure 10-2 Figure 10 Figure 10-3 Figure 10-4 Figure 10-4 Figure 10-10 Figure 10-10 Figure 10-24 Figure 10-24 Figure 10-47 Figure 10-47 Figure 10-49 Figure 10-49 Figure 10-50 Figure 10-50 Figure 10-57 Figure 10-57 Chapter 11 Figure 11-22 Figure Il-22 Chapter 15 Table 15-3 Table 15-3 Table 15-4 (p.1 & 2) Table 15-4 (p.1 & 2)

Table 15-7 Table 15-7 Table 15-8 Table 15-8 Table 15-13 (p. 2) Table 15-13 (p. 2)

Table 15-19 (p.1) Table 15-19 (p.1)

Table 15-42 Table 15-42 I999. Update

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Table 15-50 Table 15-50 t

Figure 15 51 Figure 15-51

Figure 15-52 Figure 15-52

Figure 15-53 Figure 15-53

Figure 15-54 Figure 15-54

Figure 15-55 . Figure 15-55

Figure 15-97 Figure 15-97

Figure 15-154 Figure 15154

Figure 15156 Figure 15-156

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U 1999 Update

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McGuire UFSAR 1999 itDATE i- i List of Effective Pages for Tables G

l The purpose of this list is to assure that the pages in the Tables section of your manual match the l' . most recent issue, as well as to show a full accounting of all tables, including those that have been l deleted.

Chapter 1 Tables -

5/1/92 1-1. Shared Facilities and Equipment-pages 1,3 9/1/93 - 1-1. Shared Facilities and Equipment-page 2 :

1/168 1-2. Design Comparison-page 1 l 5/1/92' l 2 Design Comparison-page 2

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5/1/92 1-2 Design Comparison-page 3 4 5/162 12 Design Comparison-page 4 5/192 1-3. Major Design Changes Since PSAR 5/1/92 1-4. Regulatory Guides-pages 1-7 9/163 1-4. Regulatory Guides-page 8 4/15/99 l 5. Piping and Instrumentation Diagrams 5/162 11-6. Regulatory Guide 1.97, Rev. 2 Review -page 1 1/12/95 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 2 l 1/1/98 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 3 1/12/95 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 4 5/1/92 1-6. Regulatory Guide l.97, Rev. 2 Review -page 5 1/12/95 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 6 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review-page 7 1/168 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 8 m 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 9

\ 2/15/99 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 10

- (d 5/162 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 11 5/1S2 , 1-6. Regulatory Guide 1.97, Rev. 2 Review-page 12 1/1265 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 13 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 14 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 15 5/1S2 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 16 2/15S9 l-6. Regulatory Guide 1.97, Rev. 2 Review -page 17 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 18 5/162 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 19 5/1/92 1-6 Regulatory Guide 1.97, Rev. 2 Review -page 20 5/1466 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 21 5/162 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 22

, $/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 23 1

5/1466 ' l-6. Regulatory Guide 1.97, Rev. 2 Review-page 24 1/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 25 5/IS2 1-6. Regulatory Guide 1.97, Rev. 2 Review -pag; 26 1/1265 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 27 1/12/95 - 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 28 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 29 l

5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 30 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 31 5/162 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 32

'- 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 33 1/168 1-6 Regulatory Guide 1.97, Rev. 2 Review page 34

fm 5/162 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 35 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 36 (V)< 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 37 1999 Update c i

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c 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 38

) 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review-page 39

" 5/1/92 l 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 40 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 41 1/1/98 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 42 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 43 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 44 1/12/95 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 45 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review-page 46 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 47 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 48 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 49 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 50 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 51 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 52 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 53 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 54 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 55 ,

5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 56 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 57 1 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 58 j

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S/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 59 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 60 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 61 l

5/14/96 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 62 l 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review-page 63 j ry 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 64 l l j 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 65 9 v 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 66 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 67 5/1/92 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 68 1/12/95 1-6. Regulatory Guide 1.97, Rev. 2 Review -page 69 4/15/99 l-7. NRC Generic Letters and IE Bulletins Response Bases (52 pages)

Chapter 2 Tables 1/12/95 2-1. McGuire Nuclear Station Population Distribution by Sector 1/12/95 2-2. Public Facilities and Institutions 1/12/95 2-3. Principle Food Crops Acreage and Yield; (1993) 5/1/92 2-4 Fish Species Composition and Abundance 1/12/95 2-5. Industries Within 10 Miles 1/12/95 2-6. Annual Aircraft Operations 1/12/95 2-7. Mix of Aircraft Types 1/12/95 2-8. McGuire Nuclear Station Traffic Counts; 1/12/95 2-9. McGuire Nuclear Station - Vicinity Climatology-page 1 5/1/92 2-9. McGuire Nuclear Station - Vicinity Climatology-page 2 5/1/92 2-9. McGuire Nuclear Station - Vicinity Climatology-page 3 5/1/92 2-10. McGuire Meteorological Survey Low Level Tower Data for Period of Oct.17,1970 Thru Oct. 16,1971 5/1/92 2-11. Diffusion Factors for Accident and Routine Releases 5/1/92 7-12. Annual Relative Frequency Distribution Station - 13881 Charlotte, NC.10n0-10n1 5/1/92 2-13. Arial Distribution of Average Relative Concentration - Ground Release 73 j 5/1/92 2-14. Wind Occurrences by Sector and Speed Class

' 5/1/92 2-15. McGuire Nuclear Station Arial Distribution of Average Relative 1999 Update l

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( 5/1/92 Concentration - Ground Release 2-16. Domestic Water Supplies 5/IS2 2-17. Catawba River Reservoir Pool Elevations 5/1/92 2-18. Estimated Flood Frequency of the Catawba River at the McGuire Nuclear Site 5/1/92 2-19. Hourly Amounts of Rainfall Excess in inches for PMF Storm Number 13 PMP Centered Over Cowans Ford Reservoir 5/1/92 2-20. Wind-Wave Data - Cowans Ford Dam 5/1/92 2-21. Wind Wave Data - McGuire Intake Structure 5/1/92 2-22. Ownership, Seismic and Spillway Design Criteria of Dams on Catawba River 5/1/92 2-23. PMP RainfallIntensities for The Critically Arranged Time Increments 5/1/92 2-24. Minimum Inflow for Drainage Area Between Lookout Shoals and Cowans Ford Dam 1/12S 5 2-25. McGuire Nuclear Station Groundwater Level Monitors 1/12/95 2-26. Population Center Distances Within A 100 Mile Radius 1/12/95 2-27. Population of Counties Within a 50 Mile Radius 1/12/95 2-28. Milk Cows Within a 50 Mile Radius (See Note 1) 1/12/95 2-29. Dairy Farms Within A 5 Mile Radius Chapter 3 Tables 5/1/92 3-1. Summary of Criteria - Structures 1/12/95 3 2. Summary of Criteria-Equipment 5/1/92 3-3. Summary of Codes and Standards for Components of Water-Cooled Nuclear Power Units By AEC Quality Group Class and ANS Safety q 1/1/98 3-4. Summary of Criteria - Mechanical System Components-pages 1,2,5,8,10-19

(' ; 2/15/99 5/1/92 3-4. Summary of Criteria - Mechanical System Components -pages 3,4,6,7,9 3-5. System Piping Classification 5/1/92 3-6. System Valve Classification 1/12/95 3-7. Electrical Systems and Components Summary of Criteria-page 1 5/1/92 3-7. Electrical Systems and Components Summary of Criteria-pages 2-6 5/1/92 3-8. Tornado Generated Missiles 5/1/92 3-9. Category 1 Structures and Missiles Protected Against 5/1/92 3-10. CRDM Housing Plug Ejection 5/1/92 3-11. Drive Shaft Ejection 5/1/92 3-12. Drive Shaft and Mechanism Ejection 5/1/92 3-13. Temperature Element Assembly Cha .icteristics 5/1/92 3-14. Pressurizer Space Valve Missiles 5/1/92 3-15. Properties of Credible Turbine Missiles 5/1/92 3-16. Internal Missiles 5/1/92 3-17. Minimum Barrier Thicknesses for all Category 1 Structures For Which Missile Protection Is Provided 4/15/99 3-18. High Energy Mechanical Piping Systems Analyzed for Consequences of ,

Postulated Piping Breaks 50/92 3-19. Moderate Energy Mechanical Piping Systems Analyzed for Consequences of Postulated Piping Breaks 5/1/92 3-20. Comparison of Duke Pipe Rupture Criteria And NRC Requirements Of Branch Technical Position APCSB 3-1 (March 1973).. ..page 14 5/13/96 3-20. Comparison of Duke Pipe Rupture Criteria And NRC Requirements C' Branch Technical Position APCSB 3-1 (March 1973).. ..pages 5 & 6 5/1/92 3-20. Comparison of Duke Pipe Rupture Criteria And NRC Requirements Of p Branch Technical Position APCSB 3-1 (March 1973).. ..page 7 Q 5/1/92 5/1/92 3-21. Postulated Break Locations in Reactor Coolant Loops 3-22. Ccmparison of Actual Moments To Reference Fatigue Analysis 1999 Update L

f3 Moments 4" ,) 3/1/92 3-23. Time-History Dynamic Solution for LOCA Loading 1/1/98 3-24. Exceptions to Criteria 1/1/98- 3-25. Damping Values for Westinghouse Supplied Equipment 1/168 3-26. Reactor Building and Interior Structure Comparison of Peak Responses 5/1/92 3-2?. Comparison of Response Spectrum And Time-History Responses

5/1/92 3-28. Maximum Blowdown LOCA Load Resultants for the Containment Interior Structure S. a92 3-29. McGuire Nuclear Station - Containment Subcompartment Pressures Cvculated Values of Differential Pressure (psi)-Across Compartments

-5/162 3-30. Design Loading Conditions 1/1/98 3-31. Codes and Spesifications for Design of Category 1 Structures and j Equipment Supports 1 1/1/98 3-32. Reactor Building Loading Combinations and Code Requirements 5/1/92 3-33. Containment Vessel Loading Combination and Code Requirements 1/1/98 3-34. Containment Materials 3-35. Deleted per 1988 Update 1/1/98 3-36. Factors of Safety Against Buckling of Shell Panels for the McGuire i Containment Vessel

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5/1/92 3-37. Comparison Between the Actual Design Differential Pressures and j the Latest Design Differential Pressures For the Major Structural j Barriers of the Interior Structure 5/1/92 3-38. Comparison Between Kalnin's Program Results and Finite Elements Results w (cps) i

(- 5/1/92 3-39. Containment Interior Structures Loading Combinations and Code

!, Requirements 1/1/98 3-40. Design Properties of Seals 1/1/98 3-41. Divider Barrier Seals Minimum Acceptable Physical Properties 5/1/92 3 42. Auxiliary Building Loading Conditions 5/1/92 3-43. Auxiliary Building Loading Combinations 5/1/92 3-44. New Fuel Storage Vault Loading Combinations 5/1/92 3-45. Factors of Safety for Category 1 Structures Against Overturning and Sliding 5/1/92 3-46. Piping Systems Included in Vibration Test Program 1/1/98 3-47. Design Conditions, Load Combinations, and Code Compliance Criteria for Duke Classes B, C, and F Piping 1/1/98 3-48. Stress Criteria For Reactor Containment Mechanical Penetrations Duke Class B 1/1/98 3-49. Stress Criteria For Supports, Restraints, and Anchors Duke Class A

1/1/98 3-50. Stress Criteria For Supports, Restraints, and Anchors Duke Classes B, C, and F 1/1/98 3-51. Stress Criteria For Safety Class 2 and 3 Cylindrical Shell Type Equipment and Components And Their Supports 5/1/92 3-52. Westinghouse Design Criteria for ASME Class 2 and 3 l Components j 5/1/92 3-53. Guard Pipe Designs Relying on ASME Code Case 1606 5/1/92 3-54. Comparison of Predicted PWHIP Response - Inclastic Pipe Element 5/1/92 3-55. Comparison of Predicted PWHIP Response -Inelastic Yield

,m Element

(") ' 5/1/92 3-56. Comparison of Predicted PWHIP Response - Inelastic Yield Element 1999 Update

gm, 5/1/92_ 3-57. HVAC Design Codes

() 5/1/92 3-58. Maximum Deflections for Reactor Internals Under Blowdown and Seismic Excitation (1-Millisecond Double-Ended Break) j 5/1/92 3-59. Maximum Stress Intensities for Reactor Internals (1-Millisecond l Pipe Break and Seismics) 5/1/92 3-60. Electrical Systems & Components Seismic Criteria 5/1/92 3-61. Post-Accident Equipment (Inside Containment) Operational !

Requirements 5/1/92 3-62. Control Complex Areas Ventilation Systems Analysis Results Chapter 4 Tables 2/15/99 41. Reactor Design Comparison Table j 1/1/98 4-2. Analytic Techniques in Core Design-page 1 j 1/12/95 4-2. Analytic Techniques in Core Design-page 2 l 4-3. Deleted Per 1992 Update 2/15/99 4-4. Reactor Core Description (Units I and 2) 1/1/98 4-5. Nuclear Design Parameters l

1/1/98 4-6. Reactivity Requirements For Rod Cluster Control Assemblies 1/1/98 4-7. Benchmark Critical Experiments

, 4-8. Deleted Per 1996 Update l 4-9. Deleted Per 1996 Update 1 l 4-10. Deleted Per 1996 Update l 4-11. Deleted Per 1996 Update 1/1/98 4-12. Axial Stability Index Pressurized Water Reactor Core With a 12 Foot Height

]

4-13. Deleted Per 1998 Update j 4-14. Deleted Per 1998 Update j y*) 4-15. ' Deleted Per 1992 Update 4-16. Deleted Per 1992 Update l 4-17. Deleted Per 1992 Update 4-18. Deleted Per 1992 Update j 2/15/99 4-19. Thermal and Hydraulic Comparison Table :

4-20. Deleted Per 1993 Update l l 9/1/93- 4-21. Void Fractions at Nominal Reactor Conditions With Design Hot i l Channel Factors 1/1/98 4-22. Statistically Combined Uncertainty Factors for Fq, F& Delta.H. and Fz l

i Chapter 5 Tables 2/15/99 5-1. System Design and Operating Parameters

l 1/1/98 5-2. Summary of Reactor Coolant System Design Transients 1/1/98 5-3. Load Combinations and Operating Conditions l 1/1/98 5-4. Faulted Condition Stress Limits for Class 1 Components (4) 4/15/99 5-5. Active and inactive Valves in the Reactor Coolant System i Boundary i 5-6. Deleted per 1998 Update l l 1/1/98 5-7. Applicable Code Addenda For Class 1 Equipment Within RCPB i j 1/1/98 5-8. Reactor Coolant Loop Piping Stress Analysis Summary ;

1/1/98 5-9. Relief Valve Discharge to the Pressurizer Relief Tank )

1/1/98 5-10. Reactor Coolant System Pressure Settings i l 1/1/98 5-11. Reactor Coolant Pressure Boundary Materials Class 1 Primary j Components p)

(

1/1/98 2/15/99 5-12. Reactor Coolant Pressure Boundary Materials Class 1 and 2 Auxiliary Components 5-13 Reactor Vessel Internals Materials for Emergency Core 1999 Update t ;

I r3-) Cooling I i-( 2/15/99 5-14. Reactor Coolant Chemistry Specification l 4/15/99- 5-15. McGuire Unit 1 Reactor Vessel Toughness Table )

9/1/93 5-16. Deleted Per 1993 Update 4/15/99 5-17. McGuire Unit 2 Reactor Vessel Toughness Table - page 1

)

l 9/1/93' 5-17. McGuire Unit 2 Reactor Vessel Toughness Table - page 2 )

5-18. Deleted Per 1993 Uplate i 1/1/98 5-19. Unit i Surveillance Weld Metal (Ht. 20291 & 12008, Linde 1092, Lot

.3854) Charpy V-Notch Impacts 9/1/93 5-20. Unit 1 Heat Affected Zone Charpy Data + 3D

- 9/1/93 5-21. Unit ! Intermediate Shell Plate C-4387-2 9/1/93 5-22. Unit 1 Intermediate Shell Plate C-4417-3 9/1/93 5-23. Unit 1 Intermediate Shell Plate C-4377-2 9/1/93 5-24. Unit 1 Lower Shell Plate C-4315-1 9/1/93 5-25. Unit 1 Lower Shell Plate C-4374-2 9/IM3 5-26. Unit 1 Lower Shell Plate C-4371-2 9/1/93 5-27. Unit 2 Heat Affected Zone Charpy Data 9/1/93 5-28. Unit 2 All Weld Metal Charpy V-Notch Impacts 9/1/93 5-29. Unit 2 Core Region 1/1/98 5-30. Reactor Coolant Leakage Detection 5-31. Deleted Per 1996 Update 1/1/98 5-32. Reactor Vessel Design Parameters 4/15/99 5-33. Surveillance Capsule Removal Schedule 5/1/92 5-34. Reactor Vessel Quality Assurance Program 1/1/98 5-35. Reactor Coolant Pump Design Parameters 1/1/98 5-36. Reactor Coolant Pump Quality Assurance Program 1/1/98 5-37. Steam Generator Design Data (n") 1/1/98 1/1/98 5-38. Steam Generator Quality Assurance Program 5-39. Reactor Coolant Piping Design Parameters 1/1/98 5-40. Reactor Coolant Piping Quality Assurance Program

'l/1/98 5-41. Design Bases for Residual Heat Removal System Operation i 1/1/98 .5-42. Residual Heat Removal System Component Data l 1/1/98 5 43. Pressurizer Design Data 5/1/92 5-44. Pressurizer Quality Assurance Program 5/1/92 5-45. Pressurizer Relief Tank Design Data !

5/1B2 5-46. Reactor Coolant System Boundary Valve Design Parameters !

1/1/98 5-47. Pressurizer Valves Design Parameters l

5/1/92 5-48. Component Supports Loading Combinations and Code i Requirements

.1/1/98 5-49. BWI Replacement Steam Generator 2/15/99 5-50. Reactor Coolant System Pressure Isolation Valves Chapter 6 Tables 5/1/92 6-1. Containment Subcompartment Pressures

.5/1/92 6-2. Containment Subcompartment Differential Pressures 5/1/92 6-3. Containment Subcompartment Differential Pressures 5/1/92 6-4. TMD Element Input Data 5/1/92 6-5. TMD Flow Path Input Data - Ventilation Duct Intact 5/1/92 6-6. TMD Flow Path Input Data - Ventilation Duct Intact ;

5/1/92 6-7. Mass And Energy Release Rates For Peak Reverse Differential i Pressure 5/1/92 6-8. Compartment Volume and Initial Condition Data For Peak Reverse Differential Pressure p 5/1/92 5/1/92 6-9. Active Heat Sink Data For Peak Reverse Differential Pressure 6-10. Upper Compartment Passive Heat Sink Data For Peak Reverse t.

f Differential Pressure 1999 Update

i

).

!i 5/1/92 6-11. Lower and Dead Ended Compartments Passive Heat Sink Data For Peak l n!'

t Reverse Differential Pressure 5/1/92 6-12 Sensitivity Studies For D.C. Cook Plant 5/14/96 6-13. McGuire Ice Condenser Design Parameters 6-14. Deleted per 1998 Update 4/15/99 6-15. Containment Sump Volume Vs. Time Peak Containment Pressure Transient 5/1/92 6-16. Containment Sump Volume Vs. Elevation (;) i 1/1/98 6-17. ECCS and Spray Flow Rates Assumed in Containment Pressure Transient 1/1/98 4 6-18. Structural Heat Sink Data 4/15/99 6-19. Comparison of Design Parameters - McGuire and D. C. Cook 5/1/92 6-20. Allowable Leakage Area For Various Reactor Coolant System Break Sizes 5/1/92 6-21. Summary Of Heat Transfer Correlations Used To Calculate Steam Generator Heat Flow In The SATAN Code 5/1/92 6-22. Mass and Energy Release Rates for Blowdown 5/1/92 6-23. Mass and Energy Release Rates for Blowdown 5/1/92 6-24. Mass and Energy Release Rates for Blowdown 5/1/92 6-25. Mass and Energy Release Rates for Blowdown

, 5/1/92 6-26. Mass and Energy Release Rates for Blowdown 5/1/92 6-27. Mass and Energy Release Rates for Blowdcwn 6-28. Thru 6-40. Deleted per 1998 Update 6-41. Deleted per 1998 Update 1/l/98 6-42. TMD Input Data - 2 Node Steam Generator Enclosure 5/1/92 6-43. TMD Input Data - 9 Node Steam Generator Enclosure (q

5/1/92 6-44. Peak Differential Pressures - 2 Node Steam Generator Enclosure 5/1/92 6-45. Peak Differential Pressure - Steam Generator Enclosure - 9 Node J 5/1/92 6-46. TMD Input Data - 2 Node Pressurizer Enclosure 4/15/99 6-47. TMD Input Data - 4 Node Pressurizer Enclosure 5/14/96 6-48. Mass and Energy Releases into Steam Generator Enclosure 5/14/96 6-49. Mass and Energy Release Rates Into Pressurizer Enclosure 5/14/96 6-50. Reactor Cavity Analysis Volumes - Cold Leg Break 5/14/96 6-51. Reactor Cavity Analysis Flow Paths - Cold Leg Break Flow 5/14/96 6-52. Mass and Energy Release Rates Into Reactor Cavity 5/14/96 6-53. Reactor Cavity Design Pressures 1/1/98 6-54. Mass and Energy Release Rates for Steam Line Rupture ,

6-55. Thru 6-61 Deleted per 1998 Update 5/14/96 6-62. Mass and Energy Release Rates for Minimum Post-LOCA Containment Pressure 6-63. Deleted per 1998 Update 1/1/98 6-64. Volume and Temperature Data For Minimum Post-LOCA Containment Pressure 5/1/92 6-65. Active Heat Sink Data For Minimum Post-LOCA Containment Pressure 5/1/92 6-66. Structural Heat Sink Data For Minimum Post-LOCA Containment Pressure 5/1/92 6-67. Basis for Peak Containment Pressure Mass and Energy Release Analysis 5/1/92 6-68. Air Return Fans and Hydrogen Skimmer Fans Failure Analysis 5/1/92 6-69. Wall Panel Design Loads (p) 5/1/92 6-70. Lattice Frame Loads Horizontial 1/2 Safe Shutdown Earthquake 1999 Update

rw 5/1/92 6-71. Local Seismic Loads on Lattice Frames Due to Single Ice I ) Basket

'5/162 6-72. Ice Conden3er Lattice Frame Loads (;) Blowdown Pressure Loads for Design Basis Earthquake (SSE) And Design Basis Accident (DBA) 5/1/92 6-73. Vertical DBA Loads On Lattice Frames 5/1/92 6-74. Vertical Friction Loads On Lattice Frames 5/1/92 6-75. Lattice Frames Summary of Maximum Stresses 5/1/92 6-76. Summary of Fatigue Analysis (;) For Lattice Frames 5/182 6-77. Ice Basket Load Summary - Minimum Test Loads 5/1/92 6-78. Ice Basket Load Summary - Basic Design Leads 5/162 6-79. Summary of Stresses in Basket Due to Design Loads 5/1/92 6-80. Ice Basket Material Minimum Yield Stress 5/1/92 6-81. Allowable Stress Limits (D + 1/2 SSE) For Ice Basket Materials 5/1/92 6-82. Allowable Stress Limits (D + SSE),(D + DBA) For Ice Basket Materials 5/1/92 6-83. Allowable Stress Limits (D + SSE + DBA) For Ice Basket Materials 5/1/92 6-84. Ice Basket Clevis Pin Stress Summary 5/1/92 6-85. Ice Basket Mounting Bracket Assembly Stress Summary 5/1/92 6-86. Ice Basket Plate Stress Summary 5/1/92 6-87. Ice Basket V-Bolt Stress Summary 5/1/92 6-88. Ice Basket - Basket End Stress Summary 5/1/92 6-89. Ice Bucket Coupling Screw Stress Summary 3 Inch Elevation (;)

5/192 6-90. Ice Bucket Coupling Screw Stress Summary 12 Foot q Elevation ( )

( j-5/1/92 6-91. Ice Bucket Coupling Screw Stress Summary 24 Foot Elevation ( )

5/192 6-92. Ice Bucket Coupling Screw Stress Summary 36 Foot Elevation (;)

5/1/92 6-93. Crane and Rail Assembly Design Loads 4/15/99 6-94. Refrigeration System Parameters 5/1/92 6-95. Lower Inlet Door Design Parameters and Loads 5/1/92 6-96. Design Loads Three Pier Lower Support Structure 5/162 6-97. Design Loads and Parameters Top Deck 5/162 6-98. Summary of Results Upper Blanket Door Structural Analysis-LOCA 5/1/92 6-99. Design Loads and Parameters Intermediate Deck 5/1/92 6-100. Summary of Waltz Mill Tests 1/12/95 6-101. Ice Condenser Allowable Limits (i) 1/12/95 6-102. Summary of Duke-McGuire Loads-Tangential Case Obtained Using the i Two-Mass Dynamic Model 1/1265 6-103. Summary of Duke-McGuire Loads-Radial Case Obtained Using the Two-Mass Dynamic Model 1/12 S 5 6-104. Summary of Load Results of Five Non-Linear Dynamic Models (Loads Are For East-West SSE Earthquake) 1/12/95 6-105. Summary of Parameters Used in the Seismic Analysis 1/12/95 6-106. Selection of Steels in Relation to Prevention of Non-Ductile Fracture ofIce Condenser Components 6-107. Deleted Per 1999 Update 4/15/99 6-108. Annulus Ventilation System Malfunction Analysis p 4/1569 6-109. Annulus Ventilation Discharge

\v' /

1/12/95 6-110. Comparison of Engineered Safety Feature Ventilation Systems With j 1999 Update

Regulatory Guide 1.52 (Rev. 0)-page 1 (O) 4/15/99 6-110. Comparison of Engineered Safety Feature Ventilation Systems With Regulatory Guide 1.52 (Rev. 0)-pages 2-5 4/15/99 6-111. Containment Piping Penetration Data (13 pages) 4/15/99 6-112. Containment Isolation Valve Test Data (15 pages) 4/15/9 > 6-113. Containment Isolation Valve Data (26 pages) 4/15/99 6-114. Containment Piping Penetrations and Isolation Valve Data (3 pages) 5/1/92 6-115. Bi directional Leakage Test Results for Typical Diaphragm Value 4/15/99 6-116. Electric Hydrogen Recombiner Typical Design Parameters 4/15/99 6-117. Parameters Used to Determine Hydrogen Generation 5/1/92 6-118. Total Hydrogen Generation 6-119. Deleted Per 1991 Update 5/1/92 6-120. Fission Product Decay Deposition in Surnp Solution 5/1/92 6-121. Total Hydrogen Generation - Westinghouse Basis (TID Release Model

- Noble Gas in Core; 0.5 Percent Zirconium-Water Reaction) 5/1/92 6-122. Total Hydrogen Generation - NRC Basis (TID-14844 Release Model -

1.5% Zirconium-Water Reaction) 4/15/99 6-123. Emergency Core Cooling System Component Parameters (2 pages) 1/12/95 6-124. Normal Operating Status of Emergency Core Cooling System Components for Core Cooling 1/1/98 6-125. Sequence of Operations: Injection to Cold Leg Recirculation - pages I and 3 4/15/99 6-125. Sequence of Operations: Injection to Cold Leg Recirculation - page 2 4/15!99 6-126. Time Sequence for Switchover to Cold Leg Recirculation 4/15/99 6-127. Failure Analysis for Switchover to Cold Leg Recirculation (4 pages) 1/1/98 6-128. Sequence of Operations: Cold Leg Recirculation to Residual 7N Containment Spray 1/1/98 6-129. Sequence of Operations: Cold Leg Recirculation to Hot Leg Recirculation 5/1/92 6-130. Maximum Potential Recirculation Loop Leakage External to Containment 4/15/99 6-131. Materials Employed for Emergency Core Cooling System Components - page 1 5/1/92 6-131. Materials Employed for Emergency Core Cooling System Components - page 2 4/15/99 6-132. ECCS Relief Valve Data 4/15/99 6-133. Single Active Failure Analysis for Emergency Core Cooling System Components Short Term Phase 4/15/99 6-134. Emergency Core Cooling System Recirculation Piping Passive Failure Analysis - Long Term Pinse 4/15/99 6-135. Valves Required to Ensure Safe Shutdown of the Reactor (6 pages) 5/1/92 6-136. Emergency Core Cooling System Shared Functions Evaluation 1/1/98 6-137. Parameters for Boron Precipitation Analysis 4/15/99 6-138. Control Area Ventilation System Failure Analysis 4/15/99 6-139. Containment Spray System Component Parameters CSS Pump Data

> 4/15/99 6-140. Types and Location ofInsulation Used in the Containment 4/15/99 6-141. Single Failure Analysis-Containment Spray System 9/1/93 6-142. Swivel Bracket Stress Summary 1/1/98 _6-141. Containment Coatings 6-144. Deleted Per 1999 Update Chapter 7 Tables 4/15/99 7-L List of Reactor Trips -page I p 5/1/92 7-1. List of Reactor Trips -page 2

\ '~ 4/15/99 7-2. Protection System Interlocks 5/14/96 7-3. Reactor Protection System Instrument Accuracies 1999 Update

r

( %, 4/15/99 7-4. Reactor Trip Correlation (4 pages)

('") '4/15/99 ' 7-5. Instrument Operating Condition for Engineered Safety Features 4/15/99 7-6. Instrument Operating Conditions for Isolation Functions 4/15/99 7-7. Interlocks for Engineered Safety Features Actuation System 4/15/99 7-8. Auxiliary Shutdown Control Panel Controls and Indicators Available for Hot Standby 1/12/95 - 7-9. Auxiliary Feedwater Pump Motor I A Control Panel Controls and Indicators Available for Hot Standby 1/12/95 710. Auxiliary Feedwater Pump Motor IB Control Panel Controls and Indicators Available for Hot Standby

'1/12/9$ 7-11. Auxiliary Feedwater Pump Turbine Control Panel Controls and Indicators Available for Hot Standby 4/15/99 7-12. Main Control Board Indicators and/or Recorders Available to the Operator (3 pages) 4/15/99 713. Main Control Board Indicators and/or Recorders Available to the Operator (2 pages) 4/15/99 7-14. Control Room Indicators and/or Recorders Available to the Operator to Monitor Significant Unit Parameters During Normal Operation (8 pages) 5/14/96 7-15. Single Failure Analysis on Containment Pressure Control System Air Return Fans and Discharge Dampers 4/15/99 7-16. Ice Condenser RTD's (3 pages) 4/15/99 7-17. Devices Actuated on ESFAS and LOOP 4/15/99 7-18. Unit Control System Interlocks 4/15/99 7-19. Reactor Trip System instrumentation Response Times (2 pages)

A 2/15/99 7-20. Engineered Safety Features Response Times kj

' Chapter 8 Tables 9/1/93 8-1. Maximum Loads to be Supplied from One of the Redundant Essential Auxiliary Power System - page 1 1/12/95 8-1. Maximum Loads to be Supplied from One of the Redundant Essential Auxiliary Power System - page 2 5/14/96 8-1. Maximum Loads to be Supplied from One of the Redundant Essential Auxiliary Power System - page 3 9/1/93 8-1. Maximum Loads to be Supplied from One of the Redundant Essential Auxiliary Power System - page 4 4/15/99 8-1. Maximum Loads to be Supplied from One of the Redundant Essential Auxiliary Power System - pages 5-10 5/14/96 8-2. Single Failure Analysis for the Offsite Pcwer Systems 9/1/93 8-3. Protective Relaying Breakdown - By Re..ay Zones 5/1/92 8-4. Monitoring Systems Analysis 8-5. Deleted Per 1999 Update 4/15/99 8-6. Equipment Shared by Both Units ,

4/15/99 8-7. Single Failure Analysis for the Onsite Power Systems - pages 1-3 5/1/92 8-7. Single Failure Analysis for the Onsite Power Systems - page 4 5/1/92 8-7. Single Failure Analysis for the Onsite Power Systems - page 5

5/1/92 8-7. Single Failure Analysis for the Onsite Power Systems - page 6 l 4/15/99 8-8. Major Loads Connected to the Diesel 5/1/92 8-9. Diesel-Generator Modeling Program Verification Data 5/1/92 810. Single Failure Analysis of the Switchyard 125 VDC System 4/15/99 8-11. 250 VDC Auxiliary Power System Loads Used for Battery

,q Sizing *

("' ) 5/14/96 8-12.125 VDC Auxiliary Control Power System Loads Used for Battery Sizing i

1999 Update L

i

)

1 i

em 5/14/96 8-13. Single Failure Analysis of the 125 VDC VitalInstrumentation and i j Control Power Systec.- page 1 4/15/99 8-13. Single Failura Analysis of the 125 VDC VitalInstrumentation and Control Power System - page 2 8-14. Deleted Per 1991 Update 5/1/92 8-15. Single Failure Analysis of the 120 Volt AC VitalInstrumentation and Control Power System 2/15/99 8-16. Load Sequencing Times Chapter 9 Tables 2/15/19 9-1. Spent Fuel Cooling System Component Design Data j 5/1/92 9-2. Spent Fuel Cooling System Failure Analysis 2/15/99 9-3. Normal Maximum Heat Load for McGuire Units 1 & 2 Spent Fuel Pools 2/15/99 9-4. Maximum Heat Load for McGuire Units 1 & 2 Spent Fuel Pools 1 5/14/96 9-5. Peak Heat Loads and Pool Temperatutes for the N Guire Units 1 & 2 Spent Fuel Taols j 5/14/96 9-6. Time to Boiling Following Loss of Forced Cooling Under Design Basis Conditions for McGuire Units 1 & 2 Spent Fuel Pools 2/15/99 9-7, Recirculated Cooling Water System-Component Design -

Parameters '

1/1/98 9-8. Nuclear Service Water Flow Requirements (gpm per channel per Unit) 1 2/15/99 9-9. Main Supply and Discharge Valve Position j 2/15/99 9-10. Nuclear Service Water System Component Design Data !

5/1/92 9-11, Nuclear Service Water System Failure Analysis -page 2 2/15/99 9-11. Nuclear Service Water System Failure Analysis -page 1 t,p) 2/15/99 9-12. Nuclear Service Water System Instrumentation and Control ]i v 5/1/92 9-13. Chemistry Specifications Nuclear Service Water 9-14. Deleted Per 1996 Update 9-15. Deleted Per 1996 Update i 5/14/96 9-16. Heat Transfer Rates to Standby Nuclear Service Water Pond I 9-17. Deleted Per 1996 Update 9-18. Deleted Per 1996 Update 9-19. Deleted Per 1996 Update 1/1/98 9-20. Conventional Low Pressure Service Water System 5/1/92 9-21. Component Cooling System Component Design Data-page 2 2/15/99 9-21. Component Cooling System Component Design Data-page 1 1/1/98 9-22. Component Cooling System Heat Load and Flow Requirements Mode 1, Unit Startup -pages 4,8,12-16 2/1589 9-22. Component Cooling System Heat Load and Flow Requirements Mode 1, Unit Startup-pages 1-3,5-7,9-11 2/15/99 9-23. Component Cooling System Valve Alignment for Various Modes of Operations 1/1/98 9-24. Component Cooling System Malfunction Analysis 2/15/99 9-25. Refueling Water System Component Design Data 5/1/92 9-26. Normal Sampling of Secondary Side for Radioactivity 9-27. Deleted Per 1992 Update 2/15S9 9-28. Compressed Gas Vessel Design Parameters 2/15/99 9-29. Compressed Air Design Parameters 9/1/93 9-30. Unit i Valves Aligned to Blackout Air Supply ~page 1 2/15/99 9-30. Unit i Valves Aligned to Blackout Air Supply-page 2 e- 2/15/99 9-31. Chemical and Volume Control System Design Parameters (Per (U w) 2/15/99 Unit) 9-31 CVCS Component Data Summary 1999 Update i

p- !

l-.

4 1

h O 5/1/92 9-33. Boron Thermal Regeneration System Component Data 2/15/99

'") ' 9-34. Boron Recycle System Component Data Summary s

l 1/1/98 9-35. Reactor Makeup Water Specifications J l 1/1/98 9-36. Auxiliary Building Fuel Handling area Ventilation System Failure 1 l Analysis 2/15/99 9-37. Comparisen of Auxiliary Building Fuel Handling Area Exhaust System j with Regulatory Guide 1.52 ]

2/15/99 9-38. Comparison of Auxiliary Building Filtered Ventilation Exhaust System with Regulatory Guide 1.52 2/15/99 9-39. Purge System Isolation Valve Design and Test Criteria 2/15/90 9-40. Comparison of Reactor Building Containment Purge Exhaust System with Regulatory Guide 1.52 Rev.1 5/1/92 9-41. Single Failure Analysis for Total Communication System 2/15/99 9-42. Failure Analysis for Lighting Systems ,

2/15/99 9-43. Diesel Generator Fuel Oil System Single Failure Analysis l 1

Chapter 10 Tables 2/15/99 10-1. Design and Performance Characteristics of the Major Equipment and Tanks 2/15/99 10-2. Main Steam Supply System Main Steam Line Safety Valves 2/15/99 10-3. Main Condenser Performance And Data !

5/1/92 10-4. Failure Mode And Effects Analysis Of The Control Systems And j Valves Of The Turbine Bypass System l 2/15/99 .10-5. Condensate And Feedwater System Feedwater Heater Data !

2/15/99 10-6. Hotwell Pump Design Data 2/15/99 10-7. Condensate Booster Pump Design Data (p

)

2/15/99 2/15/99 10-8. Steam Generator Feedwater Pump Design Data 10-9. Auxiliary Feedwater System Motor Driven Pump Design Data 5/1/92 10-10. Auxiliary Feedwater System Turbine Driven Pump Design Data 5/1/92 10-11. Component Failure Analysis for Condensate and Feedwater System 5/1/92 10-12. Component Failure Analysis for Auxiliary Feedwater System 2/15/99 10-13. Auxiliary Feedwater System Instrumentation and Controls 2/15/99 10-14. Condensate Polishing Demineralizer Design Data 10-15. Deleted Per 1992 Update 1016. Deleted Per 1992 Update 10-17. Deleted Per 1992 Update 10-18. Deleted Per 1992 Update 10-19. Deleted Per 1992 Update 10-20. Deleted Per 1992 Update 2/15/99 10-21. Steam Generator Blowdown System Component Design Data 10-22. Deleted Per 1992 Update 10-23. Deleted Per 1999 Update 2/15/99 10-24. "C" Heater Drain Tank Pump Design Data 2/15/99 10-25. "G" Heater Drain Tank Pump Design Data Chapter 11 Tables 5/14/96 11-1. Parameters Used in the Calculation of Reactor Coolant Fission Product Activities During Normal Operation 5/1/92 11-2. Design Basis Tritium Production for One Unit 5/1/92 11-3. Reactor Coolant Fission and Corrosion Product Activities During Normal Operation 5/1/92 11-4. Reactor Coolant Fission and Corrosion Product Activities During Normal Operation (n) v' 5/1/92 5/1/92 11-5. Parameters Used in Calculating Main Steam Iodine Concentrations 11-6. Main Steam lodine Concentrations Resulting From Steam Generator 1999 Update

1 I

l m - Tube Le*k

{v) 5/14/96 11-7. Design Jasis Source Strengths for Radioactive Waste Systems Input

- Streams 5/1/92 11-8. Maximum Volume Control Tank Activities 5/1/92 11-9. Steam Generator Blowdown Concentrations 5/1/92 11-10. Liquid Waste System Component Design Parameters l 5/1/92 11-11. Estimates of Annual Liquid Waste Quantities from Two Units Il-12. Deleted Per 1992 Update i l1-13. Deleted Per 1992 Update i1-14. Deleted Per 1992 Update Il-15. Deleted Per 1992 Update 5/1/92 Il-16 Estimates of Radioactivity Concentration in Hydro Station Discharges Downstream of McGuire 5/1/92 i:-17. Estimated Doses from Liquid Releases 5/1/92 Il-18. Waste Gas Tank Normal Inventories 5/1/92 11-19. Waste Gas System Component Data 5/1/92 20. Waste Gas System Instrumentation - Design Parameters -pages 1,3 2/15/99 11-20. Waste Gas System Instrumentation Design Parameters -page 2 5/1/92 11-21. Reduction in Reactor Coolant System Radioactive Fission Product Gaseous Activity 5/14/96 11-22. Parameters Used to Estimate Annual Average Airborne Radioactivity Releases from Two Units 5/1/92- Il-23. Estimates of Annual Radioactivity Releases in Gaseous Waste from Two Units (Curies) 5/1/92 11-24. Gaseous Discharges for 1971 From Westinghouse PWR Plants 5/1/92 11-25. Release Points Data n 5/1/92 11-26. Estimated Doses From Gaseous Releases

'(' 5/14/96 11-27. Liquid Process Radiation Monitoring Equipment-page 1 2/15/99 11-27.1.iquid Process Radiation Monitoring Equipment -page 2 2/15/99 11-28. Airborne Activity Process Radiation Monitoring Equipment 5/1/92 11-29. Estimated Maximum Specific Activities Input to Nuclear Solid Waste Disposal System 5/1/92 11-30. Nuclear Solid Waste Disposal System Component Design Parameters (Two Units) 5/1/92 11-31. Estimated Maximum Volumes Discharged from Nuclear Solid Waste Disposal System (Two Units) 5/1/92 11-32. Estimated Maximum Isotopic Activity Discharged from Nuclear Solid Waste Disposal System (Two Units) 5/14/96 11-33. Estimated Doses Concerning Critical Pathways to Man for Radionuclides Releases to the Environment 5/14/96 11-34. Examples of Analytical Sensitivity Versus Permissible and Discharge Canal Concentrations Chapter 12 Tables 5/1/92 12-1. Design Radiation Zones 5/1/92 12-2. Minimum Shield Thicknesses 5/1/92 12-3. Primary Shield Description 5/1/92 12-4. Parameters Used for Design Basis Accident Analysis of Control Roorn Direct Dose 5/14/96 12-5. Design Basis Accident Containment Source Strength (gammas /cc-sec) vs (hours after release) 5/1/92- 12-6. Design Basis Source Strengths for Fluids n 5/1/92 12-7. Design Basis Source Strengths for Demineralizers lV L 5/1/92 5/1/92 12-8. Design Basis Source Strengths For Filters 12-9. Reactor Coolant System Nitrogen-16 Activity 1999 Update

l ri 5/1/92 10. Design Source Strengths for Outside Storage Tanks

) 5/1/92 12-11. Area Radiation Monitors - page 1 V

1/12/95 12-11. Area Radiation Monitors page 2 5/1/92 12-11. Area Radiation Monitors - page 3 5/14/96 12-12. Annual Station Dose Estimates (person-rem /yr) 5/14/96 12-13. Estimated Occupancy Times During Normal Operations and Anticipated Occurrences (man-hrs /wk) 5/1/92 i2-14. Estimated Occupancy Times During A Refueling Outage (man-hrs)- page 1 5/14/96 12-14. Estimated Occupancy Times During A Refueling Outage (man-brs)- page 2 5/14/96 12-15. Estimated Occupational Dose by Job Function 5/14/96 12-16. Estimates of Airborne Radioactive Contamination in the Containment 5/1/92 12-17. Estimates of Airborne Radioactive Contamination in the Auxiliary Building Room l 5/1/92 12-18. Estimates of Airborne Radioactive Contamination in the Turbine Building 5/1/92 12-19. RCA and RCA Control Points 1/1/98 12-20. Design Source Strengths for the Retired Steam Generator Storage Facility Chapter 13 Tables 5/1/92 13-1. To Be Provide'd Chapter 14 Tables 5/1/92 14-1. Preoperational and Startup Test Schedule 5/1/92 14-2. Power Ascension Test Program 5/1/92 14-3. Steam Generator Water Hammer Test (Unit 1) Abstract h

i }

U Chapter 15 Tables 15-1. Deleted Per 1993 Update 1/1/98 15-2. Summary of Accidents Analyzed With Computer Codes - 3 pages 4/15/99 15-3. Summary of Computer Codes and Methodologies Used in Accident Analyses 4/15/99 15-4. Summary ofInput Parameters for Accident Analyses- pages I and 2 1/1/98 15-4. Summary ofinput Parameters for Accident Analyses -pages 3 and 4 15-5. Deleted Por 1992 Update 15-6. Deleted Per 1992 Update 4/15/99 15-7. Rod Dror Times Used in FSAR Analyses 4/15/99 15 8. Trip Points and Time Delays to Trip Assumed in Accident Analyses 15-9. Deleted Per 1992 Update 2/15/99 15-10. Iodine and Noble Gas Inventory in Reactor Core and Fuel Rod Gaps

5/1/92 15-11. Reactor Coolant Specific Activities for Iodine and Noble Gas Isotopes 5/1/92 15-12. Environmental Consequences-page 3

-2/15/99 15-12. Environmental Consequences-pages 1-2 1/1/98 15-13. Time Sequence of Events for Incidents Which Cause an increase In Heat Removal By The Secondary System - page 1 4/15/99 1513. Time Sequence of Events for Incidents Which Cause an Increase In Heat Removal By The Secondary System - page 2 5/1/92 15-14. Parameters for Main Steam Line Break Dose Analysis 9/1/93 15-15. Parameters for Loss of External Load Dose Analysis (gV) 1/1/98 15-16. Time Sequence Of Events For Incidents Which Cause A Decrease In Heat Removal By The Secondary System 1999 Update

f (m., - 1/1/98 .15-17. Time Sequence of Events for Incidents Which Cause in a Decrease in

("j ' Reactor Coolant System Flow 2/1569 15-18. Parameters for Locked Rotor Do;e Analysis i 4/15/99 15-19. Time Sequence of Events for Incidents which Cause Reac:ivity and }

' Power Distribution Anomalies - page 1 l 1/1/98 15-19. Time Sequence of Events for Incidents which Cause Reactivity and Power Distribution Anomalies - pages 2 and 3 l

j 1/1/98 15-20. Parameters Used in the Analysis of the Rod Cluster Control Assembly Ejection Accident 5/1/92 15-21. Parameters for Rod Ejection Accident Dose Analysis-page 1 1/168 15-21. Parameters for Rod Ejection Accident Dose Analysis-page 2 15-22. Deleted per 1998 Update ~

)

1/1/98 15-23. Time Sequence of Events For Incidents Which Cause A Decrease in Reactor Coolant Inventory 2/15/99 15-24. Parameters for Steam Generator Tube Rupture Dose Analysis 15-25. Deleted per 1998 Update l 15-26. Deleted per 1998 Update ;

15-27. Deleted Per 1996 Update 15-28. Deleted Per 1996 Update.

15-29. Deleted Per 1996 Update 15-30. Deleted Per 1996 Update 15-31. Deleted per 1998 Updaw 15-32. Deleted per 1998 Update '

5/1/92 15-33. Parameters for LOCA Offsite Dose Analysis 1/12/95 15-34. Parameters for LOCA Control Room Dose Analysis 5/1/92 15-35. Maximum McGuire Spent Fuel Assembly Fission Product Inventories Assumed for Fuel Handling Accidents pi i 15-36. Deleted Per 1992 Update 5/1/92 15-37. Parameters for Postulated Instrument Line Break Accident Analysis 15-38. Deleted per 1998 Update 1/1/98 15-39. Parameters Used to Evaluate Tornado Missile Impact On Spent Fuel 5/1/92 15-40. Parameters Used to Evaluate LOCA During Lower Containment Pressure Relief 2/15B9 15 41. Parameters for Single Uncontrolled Rod Withdrawal Dose Analysis 4/15B9 15-42. Input Parameters Used in the LOCA Analyses (B&W Evaluation Model) 1/1/98 15-43. Large Break LOCA Time Sequence of Events (B&W Evaluation Model) 1/lB8 15-44. Large Break LOCA Results Fuel Cladding Data (B&W Evaluation Model) 1/1/98 15-45. Maximum Injected ECCS Flows Assumed in LBLOCA Analyses 1/1/98 15-46. Parameters for Post-LOCA Subcriticality Analysis 15-47. Deleted per 1998 Update 15-48. Deleted per 1998 Update 1/168 15-49. Small Break LOCA Results Fuel Cladding Data 4/1569 15-50. Minimum ECCS Flow Assumed in SBLOCA Analyses 1/1/98 15 51. Small Break LOCA Time Sequence of Events im 1999 Update

p ll l- !

p McGuire UFSAR i j' List of Effective Pages for Figures V

The purpose of this list is to assure that the pages in the Figures section of your manual match the most recent issue, as well as to show a full accounting of all figures. No effective date next to the figure title indicates that the figure ( most likely an 11 x 17 ) was issued with the original conversion to the Bookmanager Format, which was effective 5/1/91.

Chapter 1 Figures 5/1/92 1 1. Duke Power Company Service Area 1-2. General Arrangement Plan at EL. 695 + 0 1-3. General Arrangement Plan at EL. 716 + 0 1-4.' General Arrangement Plan at EL. 733 + 0 and 739 + 0 1-5. General Arrangement Plan at EL.750 + 0 1-6. General Arrangement Plan at EL. 760 + 6 and 767 '+ 0 4/15/99 l-7. General Arrangement Plan at EL. 786 + 0 1-8. General Arrangement Longitudinal Section 1-9. General Arrangement Containment and Reactor Building Unit 1 - Plan at EL. 696 + 11 J 4/1/98 1 10. General Arrangement Containment and Reactor Building Unit 1 - Plan at EL. 725 + 0 1-11. General Arrangement Containment and Reactor Building Unit 1 - Plan at EL. 738 + 0 1-12. General Arrangement Containment and Reactor Building Unit 1 - Plan at EL. 768 + 2%

4/1/98 1-13. General Arrangement Containment and Reactor Building Unit 1 - Plan at EL. 778 + 10 p 1-14. General Arrangement Containment and Reactor Building Unit 1 - Plan t i at EL. 822 + 10 and 841 + 10 V l-15. General Arrangement Containment and Reactor Building Sections 2/15/99 l 16. General Arrangement Containmer.t and Reactor Building

. Sections 4/15/99 1-17. Reactor Building General Arrangement Plans at EL. 806 + 5 and 818 + 11 l

Chapter 2 Figures 1/12/95 2-1. General Area Map 1/12/95 2-2. Universal Transverse Mercator Grid Coordinates 1/12/95 2-3. Site Topography 5 Mile Radius 2/15/99 2-4. Plot Plan and Site Area 1/12/95 2-5. Distances from Release Points to the Exclusion Area 1/12/95 2-6. Population Center Distances within a 100 Mile Radius l 1/12/95 2-7. Population of Counties within a 50 Mile Radius 5/1/92 2-8. Population 0-10 Mile Radius l 5/1/92 2-9. Population 0-10 Mile Radius 5/1/92 2-10. Population 0-10 Mile Radius 5/1/92 2-11. Population 0-10 Mile Radius 5/1/92 2-12. Population 0-10 Mile Radius 5/1/92 2-13. Population 0-10 Mile Radius 5/1/92 2-14. Population 10-50 Mile Radius 5/1/92 2-15. Population 10-50 Mile Radius 5/1/92 2-16. Population 10-50 Mile Radius 5/1/92 2-17. Population 10-50 Mile Radius i

n 4' 5/1/92 5/1/92 2-18. Population 10-50 Mile Radius 2-19.- Population 10-50 Mile Radius k 5/1/92 2-20. Low Population Zone - 5.5 Mile Radius l'

1999 Update

p' ..

t

,. k m- - 5/1/92 - f 2-21l Low Population Zone ; 5.5 Mile' Radius .

d s

M) -5/1/921

!5/1/92

. 2-22. Low Population Zone - 5.5 Mile Radius '

2-23< Low Population Zone - 5.5 Mile Radius '

4 5/1/92 L2-24. Low Population Zone - 5.5 Mile Radius 1 I 5/1/92) 2-25. Low Population Zone - 5.5 Mile Radius - j

5/1/92 2-26. Peak Attendance - Recreation Areas 0-5 Miles .

15/1/92 2-27; Peak Attendance Recreation Areas 5-10 Miles -

5/1/92 L 2-28. Public Facilities and Institutions ,

1- '5/1/924 .2-29; Land Use (Acres) within a 50 Mile Radius L ,

, 5/1/92 2-30.' Milk Cows within a 5.) Mile Radius '

L ? 5/1/92.. 12-31;' Milk Cows within a 5 Mile Radius

-5/1/92 2-32/ Existing Land Use 0-2 Miles 5/1/92 - 2-33. Duke Owned Land within Low Population Zone L

, ' 5/1/92 : ' 2-34. Training and Technology Center Site Plan i

' 5/1/92 : 2-35. Routes, Locations, and Industries in Vicinity l l

5/1/92 : 2-36. Pipeline Details L 5/1/92 : ' 2-37. Tornadoes 1916-55 1

- 5/1/92 - 2-38.1 Vicinity Topography - Plan View l 5/1/92 2-39. Vicinity Topography Profile .

5/1/92 2-40. VicinityTopography-Profile

-2/15/99! 2-41. Plan View'of Meteorological Instruments 2/15/99 2-42. Relative Elevations of MeteorologicalInstruments 5/1/92. 2-43. Relative Concentration Frequency Distribution - 762 Meters

5/1/92 2-44. Relative Concentration Frequency Distribution - 8842 Meters 5/1/92 2-45. Relative Concentration Frequency Distribution 8842 Meters L 5/1/92 . 2-46. Area Distribution of Average Relative Concentration Ground h Release I

5/1/92; 2-47.. Area Distribution of Average Relative Concentration - Ground I b Release -

'^

5/1/92L 2-48. Area Distribution of Average Relative Concentration - Ground j Release . -1 l 5/1/92 2-49.~ Relative Concentration Frequency Distribution - 762 Metera ;

lD 5/1/92 2-50. Water Use 20 Mile Radius 2-51. Dams and Dikes 2-52. Maximum Fetch -

.2-53. Slope Protection Intake and Discharge Area l L

2 54.- Intake Channel and Discharge Canal Cross Sections )

2-55. Site Drainage Map

, 5/1/92 2-56. Building Access Point Locations 5/1/92 2-57. Discharge Rating Curve for Highway N.C. 73 Near Cowms Ford 5/1/92 2-58. Cowans Ford Dam Breach Hydrographs 4/1/98- 2-59. Backwater Area for Postulated Cowans Ford Dam Breach 4/1/98 2-60. Roof Plan

~ 2-61; Lake Norman Water Surface Elevation 2-62. Reactor and Auxiliary Buildings Groundwater Drainage System 2-63. Reactor and Auxiliary Buildings Groundwater Drainage System Sections and Details 2-64. Structure Foundation Profile 2-65. Structure Foundation Profile l:

h, l Chapter 3 Figures L

5/1/92: 31. Wind Pressure Distribution on Reactor Building n 5/1/92-5/1/92

' 3-2. Turbine Building Tornado Wind Distributions 3-3. Fire Protection System Piping Penetration Detail

- :- 5/1/92 . .'3-4. Turbines Missiles Projected Areas (Low Pressure Turbine Rotor l

1999 Update -

. l l 1 i,

i i

( Discs) !

l () : 5/1/92 1/1/98 3-5. Loss of Reactor Coolant Accident Boundary Limits 3-6. Location of Postulated Breaks l

3 5/1/92 3-7. Analytical Method for Resolving Pipe Break Consequences I 5/1/92 3-8. Reactor Coolant Loop Model !

5/1/92 3-9. Main Steam and Feedwater Routing Plan Outside Containment 5/1/92 l

3-10. Main Steam and Feedwater Routing Elevation Outside :

Containment i 5/1/92 3-11. Main Steam Routing Plan Outside Containment l 5/1/92 312. Main Steam Routing Elevation Outside Containment Nearest Reactor l

Building Wall J 5/1/92 3-13. Main Steam Routing Elevation Outside Containment Fanhest From !

Reactor Building Wall !

5/1/92 3-14. Main Feedwater Routing Plan Outside Containment !

5/1/92- 3-15. Main Feedwater Routing Elevation A-A Outside Containment I 5/1/92 316. Response Acceleration Spectra 5/1/92 3-17. Response Acceleration Spectra

! 5/1/92 3-18. Response Acceleration Spectra ;

5/1/92 3-19. Multi-Degree of Freedom System 3-20. Reactor Building Interior Structure - Mass Model 3-21. Auxilary Building Mass Model 5/1/92 3-22. Reactor Building ist and 2nd Horizontal Mode Shapes ,

5/1/92 3-23. Reactor Building ist and 2nd Vertical Mode Shapes l 5/1/92 3-24. Reactor Building - Shear Force (Ib/in) Due to SSE l 5/1/92 3-25. Reactor Building - Meridional Force NO (lb/in) Due to SSE !

5/1/92 3-26. Reactor Building - Meridional Moment M0 (ib/in) Due to SSE 5/1/92 3-27. Reactor Building - Membrane Shear N (Ib/in) Due to SSE j (p) 5/1/92 3-28. Reactor Building-Hoop Force NO (Ib/in) Due to SSE 5/1/92 3-29. Reactor Building-Honp Moment M0 (in.lb/in) Due to SSE 5/1/92 3-30. Containment Interiot Structure, First Four Horizontal Mode Shapes, North-South Direction 5/1/92 3-31. Containment Interior Structure, First Four Horizontal Mode Shapes, East-West Direction 5/1/92 3-32. Containment Interior Structure - First Two Vertical Mode Shapes 5/1/92 3-33. Containment Interior Structure Response Loads Due to SSE in the North-South Direction 5/1/92 3-34. Containment Interior Structure Response Loads Due to SSE in the East-West Direction 5/1/92 3-35. Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, North-South Direction, Elevation 738.22 5/1/92 3-36. Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, North South Direction, Elevation 768.22 5/1/92 3-37. Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, l North-South Direction, Elevation 789.47 l 5/1/92 3-38. Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, North-South Direction, Elevation 817.92 5/1/92 3 39. Response Acceleration Spectrum, Damping = 0.02, Reactor Interior, l

North-South Direction, Elevation 841.85 l 5/1/92 3-40. Reactor Building and Base Roc! Finite Element Representation

! 5/1/92 3-41. Reactor Building First Horizontal Mode

, 5/1/92 3-42. Reactor Building Second Horizontal Mode n 511/9 2 3-43. Reduced Model ofInterior Building Response Acceleration Spectrum.

Damping = 0.02, Reactor Interior, East-West Direction, Elevation

)-

738.22 1999 Update i

i I

L.O 5/1/92 ' 3-44. Combined Interaction Model Response Acceleration Spectrum, Damping

(' = 0.02, Reactor Interior, East West Direction, Elevation 738.22 5/1/92 3-45. Reduced Model ofInterior Building Response Acceleration Spectrum, i Damping = 0.02, Reactor Interior, East West Direction, Elevation J

777.60 l

5/1/92 3-46. Combined Interaction Model Response Acceleration Spectrum. Damping J

= 0.02, Reactor Interior, East-West Direction, Elevation I

, 777.60 5/1/92 3-47. Reduced Madel ofInterior Building Response Acceleration Spectrum.

Damping = 0.02, Reactor Building, North-South Direction, Elevation 768.30 5/1/92 3-48. Combined Interaction Model, Response Acceleration Spectrum, Damping = 0.02, Reactor Building, North-South Direction, Elevation 768.30 5/1/92 3-49. Respo ise Acceleration Spectrum, Damping = 0.02, Reactor Interior, North-South Direction, Elevation 768.22 5/1/92 3-50. Dynamic Analysis Model of Typical Piping System 5/1/92 3-51. Dynamic Analysis Model of Typical Piping System 5/1/92 3-52. Typical Envelope Horizontal Response Spectra for Analysis Comparison 5/1/92 3-53. Typical Verticle Response Spectra for Analysis Comparison 3-54. Typical Reactor Building and Containment Vessel Details 3-55. Reactor Building, Base Slab, Reinforcing, Bottom Radial Bars, - l Bottom Layer El. 717' + 4 3/4" 3-56. Reactor Building, Base Slab, Reinforcing Bottom Radial Bars, Top p)

(V Layer Elevation 717' + 71/2" 3-57. Reactor Building, Base Slab, Reinft:ing Top Radial Bars, Bottom Layer Elevation 721' + 10 3/4" 3-58. Reactor Building, Base Slab El. 723' + 0", Reinforcing, El. 717'

+6", El. 717' +9",722' + 0" and El. 722' + 3" 3 59. Reactor Building, Base Slab, Reinforcing Top Radial Bars, Top Layer Elevation 722' + 1 1/2" 3-60. Reactor Building, Concrete Shell, Developed Elevation -

Reinforcing El. 722 + 6 Thru El. 875 + 41/2 3-61. Reactor Building, Concrete Shell, Developed Elevation -

Reinforcing El. 722 + 6 Thru El. 875 + 41/2 3-62. Reactor Building - Equipment Hatch Reinforcing 3-63. Reactor Building, Inner Plan of Dome, Reinforcing 3-64. Reactor Building, Outer Plan of Dome, Reinforcing 3-65. Analysis of Reactor Building Penetration Space Frame Mathematical Model 3-66. Containment Vessel and Equipment Anchorage Details 3-67. Personnel Lock and Equipment Hatch Details 3-68. Typical Penetration Details 3-69. Reactor Building Containment Vessel, Cylinder Plate Layout and Penetration Location 3-70. Containment Vessel Penetration Detailt 3-71. Reactor Building Containment Vessel, Base Liner Plate, Anchors and Embedded Items 3-72. Reactor Building Containment Vessel, Base Liner Plate, Test Channel Layout o 5/1/92 3-73. Containment Vessel As Built Overall Dimensions and Plate Thicknesses l 5/1/92. 3 74. Buckling Factors of Safety Comparison Between the McGuire and 1999 Update

)

' Catawba Stations 5/1/92- 3 75. Break in Element #1 '-Ice Condenser, Transient Pressure in

, . Compartments 7,8, and 9 5/1/92 3-76. Break in Element #1 - Ice Condensor, Pressure Transients in Compartments 10,11, and 12 5/1/92 3-77. Break in F'ement #1 '-Ice Condensor, Pressure Transients in Compartmems 13,14, and 15

, ~5/1/92 - 78.~ Break in Element #1 - Ice Condensor, Pressure Transients in

'. Compartments 16,17, and 18 5/1/92 3-79. Break in Element #1 -Ice Condensor, Pressure Transients in Compartmmts 19,20, and 21 5/1/92 ' 3-80. Break inDement #1 -Ice Condensor, Pressure Transients in .

Compartments 22,23, and 24 5/1/92- .3-81. Break in Element #1 - Ice Condensor, Pressure Transients in Compartments 25,29, and 33 5/1/92 3-82. Fourier Series Representation of Dynamic Loads 5/1/92 3-83. Compartment Layout - Plan at Equipment Rooms Elevation 5/1/92 3-84. Compartment Layout - Co.'tainment Section View 5/1/92 '3-85. Layout of Containment Shell 5/1/92- 346. Civil-Environmental Division Partial Organizational CLart 5/1/92 3-87. Reactor Building, First Horizontal Mode, f = 4.96478 cps (Kalnin's) 5/1/92 3-88. Reactor Building, First Horizontal Mode, f = 4.97 cps (Finite .

Elements) 5/1/92 3-89. Containment Vessel, First Horizontal Mode, f = 9.284 cps (Kalnin's) 5/1/92 3-90. Containment Vessel, First Horizontal Mode, f = 9.3234 cps (Finite

( 5/1/92 Elements) 3-91. Containment Vessel, Second Horizontal Mode, f = 25.69 cps (Kalnin's) 3/1/92 3-92. Containment Vessel, Second Horizontal Mode, f = 25.660 cps (Finite Elements) 5/1/92 3-93. Containment Vessel, First Venical Mode 5/1/92 3-94. Containment Vessel, First Vertical Mode 5/1/92 3-95. Portion of the Operating Deck 5/1/92 ~ 3-96. Operating Deck Strudi Finite Elements Representation 5/1/92 3-97. Comparison of Program Results Fixed Boundary Conditions 5/1/92 3-98. Comparison of Program Results Pinned Boundry Conditions 4/1/98 3-99. Reactor Building -Units 1 & 2 Pressure Seals and Gaskets 4/1/98 3-100. Reactor Building - Units 1 & 2 Pressure Seals and Gaskets 3-101. Reactor Building - Units 1 & 2 Pressure Seals and Gaskets 3-102. Diegl Generator Area, General Arrangement Floo: Plan, El. 736 +6, Roof Plan, El. 764 + 7 3-103. Diesel Generator Area General Arrangement Cross Section 3-104. Auxiliary Building, Fuel Building, General Arrangement Plan at El.

760+6 3-105. Auxiliary Building, Fuel Building, General Arrangement Plan at El.

778+10 3106. Auxiliary Building, Fuel Building, General Arrangement, Longitudinal Section Thru Fuel Pool 3-107. Auxiliary Buihiing, Fuel Building, General Arrangement, Transverse Section at Cask Area 3-108. Auxiliary Building, Floor El. 733 + 0, GenerM Arrangement, Battery Room Plan 3-109. Auxiliary Building, El. 750 + 0, General Arrangement, Cable Room 1999 Update

r Plan (y") 3-110. Auxiliary Building. El. 767 + 0, General Arrangement, Control Room Plan 3-111. Reactor Building Foundation and its Connection to Reactor Building Shell and Crane Wall (Reinforcement Details) 5/1/92 3-112. Reinforcement Arrangement Between the Auxiliary Building Foundation and a Typical Vertical Wall 5/1/92 3-113. Vibration Checkout Functional Test Inspection Points 5/1/92 3-114. Vibration Checkout Functional Test Inspection Points 5/1/92 3-115. Time-History Dynamic Solution for LOCA Loading 5/1/92 3-116. Theoretical Solution 5/1/92 3-117. PWhip Verification Example Inelastic Pipe Element 5/1/92 3-118. PWhip Verification Example Inelastic Yield (U-Bar) Element Plastic Behavior 5/1/92 3-119. Theoretical Solution 5/1/92 3-120. PWhip Verification Example Inelastic Yield (U-Bar) Element Initial Gap Effect 5/1/92 3-121. Test Chamber Temperature Profile for Accident Environment Simulation 4/1/98 3-122 Reactor Coolant Loop Model for Steam Generator Replacement 4/1/98 3-123 Reactor Coolant Loop Model for Steam Generator Replacement 4/1/98 3-124 Reactor Coolant Loop Model for Steam Generator Replacement 4/1/98 3-125 Reactor Coolant Loop Model for Steam Generator Replacement (N Chapter 4 Figures

(" ) 1/12/95 4-1.17 x 17 Fuel Assembly Cross Section 4-2. Deleted Per 1993 Update 4-3. Deleted Per 1993 Update 5/1/92 4-4.17 x 17 Optimized Fuel Assembly Outline 2/15/90 4-5. Fuel Rod Schematic 4-6. Deleted Per 1993 Update 4-7. Deleted Per 1993 Update 5/1/92 4-8. Typical Clad and Pellet Dimensions as a Function of Exposure 5/1/92 4-9. Representative Fuel Rod Internal Pressure and Linear Power Density for the Lead Burnup Rod as a Function of Time 5/1/92 4-10. Lower Core Support Assembly (Core Barrel Assembly) 5/1/92 4-11. Upper Core Suppon Structure 5/1/92 4-12. UHI Upper Support Column 5/1/92 4-13. Plan View of Upper Core Support Structure 5/1/92 4-14. Full Length Rod Cluster Control and Drive Rod Assembly with Interfa d 3 Components 5/1/92 4-15. Full Length Rod Cluster Control Assembly Outline 5/1/92 4-16. Full Length Absorber Re:. Wnit 1) 5/1/92 4-17. Fulllength Absorber Rod (Unit 2) 5/1/92 4-18. Burnable Poison Assembly 5/1/92 4-19. Burnable Poison Rod Cross Section (Pyrex) 5/1/92 4-20. Burnable Poison Rod (WABA) Cross Section 5/1/92 4-21. Primary Source Assembly 4 22. Deleted Per 1996 Update 5/14/96 4-23. Thimble Plug Assembly (Conceptual) 5/1/92 4-24. Full Length Control Rod Drive Mechanism

,,'j 5/1/92 5/1/92 4-25. Full Length Control Rod Drive Mechanism Schematic 4-26. Nominal Latch Clearance at Minimum and Maximum Temperature 1999 Update J

,1 r

g);

(

5/1/92' 5/162.

/ 4-27. Control Rod Drive Mechanism Latch Clearance Thermal Effect 4-28. Maximum Tolerable Seismic Moments vs. Calculated Seismic Moments -

Full Length CRDM ;

5/1621 4-29. Schematic Representation of Reactor Core Model -

5/14S6- 4-30, FuelLoading Arrangement ,

' 5/1/92 . 4-31, Typical Reload Core Fuel Loading Arrangement 5/162- 4 32. Production and Consumption of Higher Isotopes

.1/1/98 33{ Typical Boron Concentration Versus Cycle Burnup with and without Burnable Poison Rods . q

'5/1466' ' 4-34. Typical Burnable Poison Rod Arrangement within an Assembly 1/168 4-35. Typical Burnable Poison Loading Pattern 5/162 '4-36. Burnable Poison Loading Pattern (Initial Core) }

- 1/1/98 . ' 4-37. Typical Normalized Power Density Distribution Near Beg' inning of I 4

Life, Unrodded Core, Hot Full Power, No Xenon 1/IS8 4-38. Typical Normalized Power Density Distribution Near Beginning of

.. Life, Unrodded Core, Hot Full Power, Equilibrium Xenon 1/198 4 39. Typical Normalized Power Density Distribution Near Beginning of Life, Control Bank D 28% Inserted, Hot Full Power, Equilibrium

. Xenon

.1/1/98' 4-40. Typical 'Vormalized Power De'n sity Distribution Near Middle of Life,

- Unrodded Core, Hot Full Power, Equilibium Xenon 1/1/98 4-41. Typical Normalized Power Density Distribution Near End of Life, Unrodded Core Hot Full Power, Equilibium Xenon 5/162 4 42. Rodwise Power Distribution in a Typical Assembly (Assembly G-9)

Near Beginning of Life, Hot Full Power, Equilibrium Xenon, l p .

Unrodded Core

! :i 5/1/92 4-43. Rodwise Power Distribution in a Typical Assembly (Assembly G-9)

Near End of Life, Hot Full Power, Equilibrium Xenon, Unrodded

Core 1

!- 5/1/92 4-44. Typical Axial Power Shapes Occurring at Beginning of Life !'

5/1/92 4-45. Typical Axial Power Slupes Occurring at Middle of Life i- 5/1/92 4-46. Typical Axial Power Shapes Occurring at End of Life li 5/1/92 4-47. Comparison of Assembly Axial Power Distribution with Core Average Axial Distribution, Control Bank D Slightly Inserted

48. Deleted Per 1992 Update s 4-49. Deleted Per 1992 Update '

4-50. Deleted Per 1992 Update 1 ]'

1/168 4-51. Maximum FQ Power Versus Axial Height During Normal Operation 4-$2. Deleted Per 1992 Update 4-53. Deleted Per 1992 Update ;

4-54. Deleted Per 1992 Update i 4-55. Deleted Per 1992 Update 4-56. Deleted Per 1992 Update

-5/1/92 4-57. Doppler Temperature Coefficient at Beginning of Life and at End of Life, Cycle 1

'5/1/92 4-58. Doppler-only Power Coefficient - Beginning of Life, End of Life, Cycle 1 5/1/92 l 4-59. Doppler-only Power Defect - Beginning of Life, End of Life, Cycle 5/1/92 - 4-60. Moderator Temperature Coefficient - Beginning of Life, Cycle 1, No Rods

, V 5/1/92 4-61. Moderator Temperature Coefficient - End of Life, Cycle 1

-5/1/92 4-62. Moderator Temperature Coefficient as a Function of Boron Concentration - Beginning of Life, Cycle 1. No Rods 1999 Update

u l.

l l .

,-~.g

-I '5/1/92 4-63. Hot Full Power Temperature Coefficient During Cycle i for the Critical Boron Concentration 5/162. , 4-64. Total Power Coefficient - Beginning of Life, End of Life, Cycle -

1 5/1/92 4-65. Total Power Defect - Beginning of Life, End of Life, Cycle 1 '

-5/1/92 4-66. Rod Cluster Control Assembly Paaern 1/1/98' : 4-67. Typical Accidental Simultaneous Withdrawal of Two Control Banks EOL, HZP Banks B and D Moving in the Same Plane 4-68.' Deleted Per 1998 Update 4-69. Deleted Per 1998 Update - .. . .

i 5/182- 4-70. Axial Offset Versus Time, PWR Core with a 12-FT. Height and 121 ,

Assemblies -

5/1/92 4-71. XY Xenon Test Thermocouple Respcase Quadrant Tilt Difference 1

~~

. . Versus Time I 5/182 4-72. ' Allowed Moderator Temperature Coefficient as a Function of % Rate.d Thermal Power 5/1/92' 4-73. Calculated and Measured Doppler Defect and Coefficients at

. Beginning of Life, Two-Loop Plant,121 Assemblies,12-Foot Core 1

- 4 74. Deleted Per 1992 Update 1

4-75. Deleted Per 1992 Update 4-76. Deleted Per 1992 Update 4-77. Deleted Per 1993 Update.

9/1/93 4-78. Measured Versus Predicted Critical Heat Flux-BWCMV '

Correlation 5/1/92 4-79. TDC Versus Reynolds Number for 26 Inch Grid Spacing A) -.

t

~

4-80. Deleted Per 1993 Update.

4-81. Deleted Per 1993 Update.

4-82. Deleted Per 1993 Update. ;

5/192 4-83. Void Fraction Versus Thermodynamic Quality H-Hsat/Hg.Hsat !

5/1/92 - 4-84. Thermal Conductivity of UO2 (Data Corrected to 95% Theoretical 'l

._ Density) !

4-85. Deleted Per 1993 Update. l

. 5/1/92 4-86. Distribution ofIncore Instrumentation l 5/1/92 4-87. Xenon Stability as a Function of Core Burnup for 10% Power Drop ;

with Rods Constant Axial Offset (%) vs. Time (hours) l 5/IS2 88.17 x 17 Mark-BW Fuel Assembly Outline

- 5/14/96 4-89. Double Encapsulated Secondary Source Assembly Chapter 5 Figures 4/IS8 5-1. Summary Flow Diagram of Reactor Coolant Sy tem 5-2.' Deleted Per 1994 Update

,5/IS2 5-3. Pump Head - Flow Characteristics 5-4. Deleted per 1998 Update 5-5. Deleted per 1998 Update 5-6. Deleted per 1998 Update 5-7. Deleted per 1998 Update 1/1/98 5-8. Reactor Coolant Loop / Supports System Dynamic -Westinghouse Structural Model 5-9. Deleted per 1998 Update

l. .

5/1/92. 5-10.' Power Operated Relief Valve Floa Characteristics i ( .

' 5-11. Deleted per 1998 Update 5-12.' Deleted per 1998 Update l'999 Update

r 5-13. Deleted per 1998 Update (m)

5/1/92 5-14. Deleted per 1998 Update 5-15. Effect of Fluence and Copper Content on Shift of RTNDT for Reactor Vessel Steels Exposed to 550GF Temperature 5/1/92 5-16. Predicted Fluence at >T and %T Locations as a Function of Full Power Service Years 1/1/98 5-17. KID Lower bound Fracture Toughness A533V (Reference WCAP 7623)

Grade B Class 1 1/1/98 5-18. Nominal Containment Sump Level Change Rate Versus Leakage Rate 1/1/98 5-19. Relationship Between Reactor Coolant System Temperature and Power 5/1/92 5-20. Reactor Vessel Head View Showing Top-Mounted Control Drive Mecht.nism Housing Locations 5/1/92 5-21. Surveillance Capsule for Unit l- Elevation View 5/1/92 5-22. Surveillance Capsule for Unit 2- Elevation View 1/1/98 5-23. Surveillance Capsule Plan View l 5/1/92 5-24. Reactor Coolant Controlled Leakage Pumps l 5/1/92 5-25. Estimated Performance Curve - Controlled Leakage Main Coolant Pump i 5/1/92 5-26. Reactor Coolant Pump Spool Piece and Motor Support Stud l 1/1/98 5-27. BWI Steam Generator 4/1/98 5-28. Summary Flow Diagram of Residual Heat Removal System j 5/1/92 5-29. Pressurizer i 5/1/92 5-30. Typical Steam Generator Lower Lateral Support l 1/1/98 5-31. Typical Steam Generator Upper Support l 5/1/92 5-32. Typical Column Assembly for the Steam Generator and Reactor l Coolant Pump g) 5/1/92 5-33. Typical Reactor Coolant Pump Lateral Support for Loops 1-2 l

(V 5/1/92 5-34. Typical Reactor Coolant Pump Lateral Support for Loops 3-4 i 5/1/92 5-35. Pressurizer Support System Elevation 5/1/92 5-36. Pressurizer Lower L.ateral Support 5/1/92 5-37. Pressurizer Upper Lateral Support 5/1/92 5-38. Typical Reactor Vessel Support 5-39. Deleted Per 1995 Update 5-40. Deleted Per 1995 Update 5-41. Deleted Per 1995 Update 5-42. Deleted Per 1995 Update 5-43. Deleted Per 1995 Update Chapter 6 Figures 4/1/98 6-1. Symbols for Flow Diagrams - pages 1 and 3 4/15/99 6-1. Symbols for Flow Diagrams - page 2 4/1/98 6-2. Symbols and System Abbreviations for Flow Diagiams

} 4/15/99 6-3. Index for Flow Diagrams 5/1/92 6-4. Sensitivity of Pressure to Air Compression Ratio 5/1/92 6-5. Steam Concentration in a Vertical Distribution Channel 5/1/92 6-6. Peak Compression Pressure Versus Compression Ratio 3/1/92 6-7. Upper Compartment Compression Pressure Versus Energy Release nor Tests at 100% and 200% of Initial DB A Blowdown Rate 4/15/99 6-8. Peak Containment Pressure Transient-pressure 4/15/99 6-9. Peak Containment Pressure Transient-Upper Containment Temperature 4/15/99 6-10. Peak Containment Pressure Transient-Lower Containment Temperature g3 4/15/99 6-11. Peak Containment Pressure Transient-SumpTemperature

( ) 1/1/98 6-12. Peak Containment Pressure Transient-Ice Melted V 1/1/98 6-13. Containment Spray Return Drains From Air Return Fan Pits ( 2 parts) 1999 Update

p .

h s

I W ;

4/1/98 6-14.- Piping Layout, FW System

615. Containment Spray Return Drains From Refueling Canal

.; - ' 5/1/92 6-16 Lice Melted Versus Energy Release for Tests at Different Blowdown

, Rates

&~ 5/1/924 L 6-17. Upper Compartment Peak Compression Pressure Versus Blowdown Rate for Tests With'175% Energy Release -

15/1/92- 6-18. Peak Reverse Differential Pressure Transient L 5/1/92 6-19J Peak Reverse Differential Pressure Transient -

5/1/92 - c 6-20, Peak Reverse Differential Pressure Transient Assuming Enhanced Lower Compartment Heat Transfer. _

l' '5/1/92 6-21. Peak Reverse Diff tential Pressure Transient Assuming Enhanced -

" Lower Compartment Heat Transfer:

5/1/92i 22. Pressure Increase Versus Deck Area From Deck Leakage Tests 5/1/92- : 6-23. Energy Release at Time of Compression Peak Pressure From i Full-Scale Stection Tests With 1-Foot Diameter Baskets ll I/168: ,

6-24. Peak Containment Temperature-Lower Containment Temperature

' Breaks

, lI/168 a 25. Peak Containment Temperature Transient - Dreak Compartment Temperature

' 6-26. Deleted per 1998 Update

-5/162! 6-27, Upper and Lower Compartment Pressure Transient for Worst Case, Break Compartment (Element 1) Having a DEHL Break 5/1/)2 6-28. Upper and Lower Compartment Pressure Transient for Worst Case Break Compartment (Element 1) Having A DECL Break 5/1/92 6-29. Plan at Equipment Rooms Elevation 5/1/92 6-30. Containment Section View 5/162 6-31. Plan View at Ice Condenser Elevation - Ice Condenser Compartments -

l( 5/1/92 _ 6-32. Layout of Containment Shell

! 5/1/92 . 6-33. TMD Code Network 5/1/92 6-34. Nine Volume Nodalization of the Steam Generator Enclosure L 15/1/92 6-35. Illustration of Choked Flow Characteristics 5/162- 6-36. Double Ended Steam Line Break in Steam Generator linclosure 5/1/92 6-37. Double Ended Steam Line Break in Steam Generator Enclosure l l.

5/1/92 . 6-38. Double Eaded Steam Line Break in Steam Generror Enclosure )

-5/162 6-39. Double Ended Steam Line Break m Steam Genecawr Enclosure i 5/1/92 6-40. Double Ended Steam Line Break in Steam Generator Enclosure l 5/IS2 6-41. Two Volume Nodalization of the Steam Generator Enclosure j

'5/1/92 6-42. Two Volume Nodalization of the Pressurizer Enclosure !

5/1/92. 6-43. Four Volume Nodalization of the Pressurizer Enclosure 5/162 6-44. Developed View of the TMD Code Network for the Reactor Cavity

- Analysis 5/162- 6-45. Flow Path Connections for the Reactor Cavity Analysis 5/1/92 6-46. Containment Model for the Reactor Cavity Analysis 5/1/92 ~ 47. Reactor Vessel Nozzle Break Supports 5/1/92 6-48._ Reactor Cavity Analysis Elenent 1 j j 5/1/92. 6-49. Reactor Cavity Analysis Element 2 5/1/92 6-50. Reactor Cavity Analysis Element 3 5/1/92 6-51. Reactor Cavity Analysis Element 4 .

L 5/162 6-52. Reactor Cavity Analysis Element 5 -

'5/162 6-53. Reactor Cavity Analysis Element 6 j 5/1S2 '6-54. Reactor Cavity Analysis Element 7 5/1/92 6-55. Reactor Cavity Analysis Element 8 5/1/92 - 6-56. Reactor Cavity Analysis Element 9 )

I '5/1/92 6-57. Reactor Cavity Analysis Element 10 5/1/92' 6-58.- Reactor Cavity Analysis Element 11 l l

1999 Update i

p l:

i? p i ,

4 w

@ #D 5/1/92. L6-59. Reactor Cavity Analysis Element 12 h 5/1/92 6-60. Reactor Cavity Analysis Element 13

' '[

'5/1/92 6-61. Reactor Cavity Analysis Element 14 -

' 5/1/92 6-62. Reactor Cavity Analysis Element 15 l E

,5/162- ~ 6-63. ' Reactor Cavity Analysis Element 16 i 5/1/92 : 6-64.~ Reactor Cavity Analysis Element 17. '

j. 5/162- 6-65. Reactor Cavity Analysis Element 18

- 5/1/92 - . 6-66. Reactor Cavity Analysis Element 19 L 5/1/92 ' 6-67. Reactor Cavity Analysis Element 20 ; i 15/1/92 . ,6-68. Reactor Cavity Analysis Element 21 j

. 5/f 92 : . 6-69.~ Reactor Cavity Analysis Element 22 '~ i 5/1/92? ,

6-70. Reactor Cavity Analysis Element 23 . ,

5/1/92' 6-71. Reactor Cavity Analysis Element 24..

l

, 5/1/92- 6-72. Reactor Cavity Analysis Element 25 - j 5/1/92 6-73. Reactor Cavity Analysis Element 26 -

_5/1/92 , 6-74. Reactor Cavity Analysis Element 27

'5/162 6-75. Reactor Cavity Analysis Element 28 L i 5/162 L .6-76. Reactor Cavity Analysis Element 29 '

5/162 ~ 6-77. Reactor Cavity Analysis Element 30 -

- 5/1S2 . 6-78.' Reactor Cavity Analysis Element 31- ,

5/162- 6-79. Reactor Cavity Analysis Element 32 ;

. I 5/1/92' 6-80. Reactor Cavity Analysis Element 33 5/1/92 . 6-81. Reactor Cavity Analysis Element 45 5/162- 6-82. Reactor Cavity Analysis Element 46' i 5/162 6-83. Reactor Cavity Analysis Element 47 '

~

5/162 6-84. Reactor Cavity Analysis Element 53 ;

y 5/1/92 5/1621 6-85. Reactor Cavity Analysis Element 54 6-86. Hot 1.xg Double Ended Guillotine Break

.l 5/1/92 = 6-87. . Hot Leg Double Ended Guillotine Break )

5/162 : 6-88. Cold Leg Double Ended Guillotine Break )

5/1/92- 6-89. Cold Leg Double Ended Guillotine Break .

5/1/92 6-90. Hot Leg Single Ended Split Break l 5/162 6-91. Hot Leg Single Ended Split Break.

5/1/92' 6-92. Cold Leg Single Ended Split Break ,

5/IS2 ' 6-93. Cold Leg Single Ended Split Break '

5/1/92 6-94. Comparison of Satan to Henry-Fauske 5/1/92 7 r

6-95. Comparison'o Satan to Moody Subcooled - 1 5/1/92 ~ 6-96. Zaloudek Measured Data Versus Modified Zaloudek Correlation 5/162 6-97. Zaloudek Short Tube Data 5/162.. 6-98. Exit Plane Quality as a Function of Upstream Pressure for Saturated Liquid 5/1/92 . 6-99. . Henry Anl 7740 Data '

J 5/1/92 - 6-100. Loft Tests 809 and 813 Gate P 1 ~

' 5/1S2 ~ 6-101. Minimum Pressure Analysis -

j 5/162. 6-102. Minimum Pressure Analysis

/! 5/182' 6-103. Minimum Pressure Analysis A 5/1/921 6-104.' Minimum Pressure Analysis ;

5/162 6-105. Minimum Pressure Analysis -

F 5/162; 6-106. Minimum Pressure Analysis 5/1/91- 6-107. Flow Diagram of Containment Air I;eturn Exchange and Hydrogen

Skimmer System 6108. Reactor Building Heating-Ventilation-Air Conditioning

5/1/92- .6-109. Containment Air Return Fan Performance Curve 7

4 5/14/96- 6-110. Hydrogen Skimmer System

\ ,5/1/92 , . 6-111. Hydrogen Skimmer Fan Performance Curve l

l

.1999 Update ~

T

O _

r

- r, i ,

r i

e y ): ,

m. , ,

9~V i -

5/14/96- . 6-112. Potential Areas of Hydrogen Pocketing and Minimum Flows (L^ [ ?5/1/92 4 5/1/92 6-113. Isometric ofIce Condenser .

114. Floor Structure f

' 5/1/92 : 6-115. Wear Slab Top Surface Area Showing Typical Coolant Piping -

Layout

_7 . 5/1/92 . _6-116. Lattice Frame Orientation

'i : 5/1/92 L 6-117. Load histribution for Tangential Seismic and Blowdown Loads in

= Analytical Model:

6-118. Lattice Frame - . ,.

.g .

~ 6-119. Lattice Frame Analysis Model ,

- 5/1/921 120. Typical Bottom Ice Basket Assembly) 5/1/92 = :. 6-121. Combination of Concentric Axial Load and Distribution Load That Will Cause Failure of a Perforated Metal Ice Condenser Basket -

L . Material Layout ?

6-122J Crane Assembly .

j 4

.. ;.6-123. Crane Rail Assembly.

-4/15/99- 6-124. Refrigerant Cycle Diagram-

+ " 5/1/92 - 16-125. Glycol Cycle to Each Containment U

5/1/92 - 6-126.1 Schematic Flow Diagrams of Air Cooling Cycle -

5/1/92. 6-127. Air Handling Unit Support Structure -

5/1/92 6-128. Flow Area Pressure Differential .

6-129. Lower inlet Door Asse.mbly . .

6-130. Details of Lower Inlet Door Showing Hinge, Proportioning Mechanism Limit Switches and Sea's 5/1/92 6-131. Inlet Door Frame Assembly 5/1/92 6-132; Inlet Door Panel Assembly .

p. ,

6-133. Lower Inlet Door Shock Absorber Assembly g 6-134 Four Loop Ice Condenser Lower Support Structure Conceptual Plan

and Sections 5/1/92 6-135. Four Loop Ice Condenser Lower Support Structure General Assembly 5/1/92 6-136. ANSYS Model Assembly 5/1/92 6-137.- Finite Element Model of Portal Frame 5/1/92- 6-138. Schematic Diagram of Forces Applied to Three Pier Lower Support Structure 5/1/92 6-139. Force Transient Hot Leg Break . j 5/1/92 6-140. DLF Spectra Hot Leg Break Force Transient I 6-14L Top Deck Test Assembly :

' 6-142.. Details of Top Deck Door Assembly ;

6-143.~ Intermediate Deck Door Assembly f ,

6-144. Air Distribution Duct .

. 5/1/97 6-145. Phase Diagram for NA2 B4 07.10 H/ Water System at One Atmosphere

5/1/92 6-146. Ice Bed Compaction Versus Time 5/1/92 . 6-147. Test Ice Bed Compaction Versus Ice Bed Height 5/1/92. ' 6148. Model of Horizontal Lattice Frame Structure ,

5/1/92 6-149. Group Six Interconnected Lattice Frames 5/1/92 6-150. Lattice Frame Ice Basket Gap 5/1/92 - 6-151. Typical Displacement Time Histories for 12 Foot Basket With End Supports - Pluct Test 5/1/92- 6-152. Non Linear Dynamic Model 5/1/92 6-153. 3 Mass Tangentiallee Basket Model

, p ,, 5/1/92 6-154. 9 Mass RadialIce Basket Model 5/1/92 6-155. 48 Foot Beam Model 5/1/92 6-156. Phasing Mass Model of Adjacent Lattice Frame Bays

' 1999 Update

.. i:

r.

l l

l q 5/1/92 6-157. Phasing Study Model, I Level Lattice Frame 300 Degrees Nonlinear j Model 5/1/92 6-158. Typical Crane Wall Acceleration 5/1/92 6-159. Typical Crane Wall Velocity -

5/1/92 6-160. Typical Crane Wall Displacement I 5/1/92 6-161. Typical Ice Basket Displacement Response 5/1B2 L 6-162. Typical Ice Basket Impact Face Response 5/1/92 6-163. Typical Crane Wall Panel Load Response 5/1/92 6-164. Wall Panel Load Distribution Obtained Using the 48-Foot Beam Model Tangential Case i 5/1B2 6-165. Wall Panel Load Distribution Obtained Using the 48-Foot Beam Model l Radial Case j 5/1B2 6-166. Ice Basket Impact Load Distribution Obtained Using the 48-Foot !

Beam Model Tangential Case 5/162 <

6-167. Ice Basket Impact Load Distribution Obtained Using the 48-Foot j Beam Model Radial Case 5/1/92 6-168. Lower Inlet Door Differential Pressure - Time History ]

9/163 6-169. Flow Diagram of Annulus Ventilation System 6-170. Reactor Building Annulus - Developed Elevation From 270G to l 90G 6-171. Reactor Building Annulus - Developed Elevation From 90G to 270 &

5/1/92 6-172. Containment Piping Penetration Classification '

1/12/95 6-172. Containment Piping Penetration Classification - page 3 5/1/92 6-173. Butterfly Valve Details 5/1/92 6-174. Aluminum Corrosion in DBA Environment n j 5/1/92 6-175. Results of Westinghouse Capsule Irradiation Tests j i 5/14/96 6-176. Flow Diagram of Safety Injection System l

'~' 5/14/96 6-177. Flow Diagram of Safety injection System 6-178. Deleted Per 1993 Update 5/1/92 6-179. NPSH and Head Capacity Curves for RHR Pumps !

5/1B2 6-180. NPSH and Head Capacity Curves for Safety Injection Pumps 5/1/92 6:181. NPSH and Head Capacity Curves for Charging Pumps !

4/15/99 U-182. ECCS Piping Layout ( 32 parts) 1/12/95 6-183. ECCS Process Flow Diagram (3 parts) 4/15/99 6-184. UHIWater Accumulator 5/1/92 6-185. Leak Rates for Bushing 5/162 6-186. Bushing Leak Rate After Severe Operation 5/1/92 6-187. Cutaway View of Motor Operated Valve Actuator 9/1/93 6-188. Flow Diagram of Control Area Chilled Water System 9/1/93 6-189. Flow Diagram of Control Area Chilled Water System 4/1/98 6-190. Flow Diagram of Control Area Chilled Water System 2/15/99 6-191. Flow Diagram of Control Area Ventilation System 6-192. Deleted Per 1993 Update 6-193. Deleted Per 1993 Update 1/12B5 6-194. Flow Diagram of Containment Spray System 5/182 6-195. Spray Nozzle Mass Distribution 4/15B9 6-196. Containment Sump ( 2 parts) 5/1/92 6-197. InterTnediate Deck Differential Pressure - Time History j 5/1/92 6-198. Zine Corrosion in DBA Environment 5/1B2 6-199. Flow From Intact and Broken Loops ,

9/1/93 6 200. Ice Basket Swivel Bracket Assembly I

,-7 1/1/98 6-201. Double-ended LBLOCA Mass and Energy Release Analysis

( ) 1/1/98 6-202. Double-ended LBLOCA Mass and Energy Release Analysis 1/1/98 6-203. Double-ended LBLOCA Mass and Energy Release Analysis 1999 Update

i

, 1/1/98 6-204. Double-ended LBLOCA Mass and Energy Release Analysis m

Chapter 7 Figures 5/1/92 7-1. Instrumentation and Control System Logic Diagram - page 1 5/1/92 7-1. Instrumentation and Control System Logic Diagram - page 2 i/12/95 7-1. Instrumentation and Control System Logic Diagram - page 3 7-1. Instrumentation and Control System Logic Diagram - pages 4-6 and 9-16 4/15/99 7-1. Instrumentation and Control System Logic Diagram - pages 7 and 8 4/15/99 7-2. Setpoint Reduction Function for Overpower and Overtemperature Delta Trips 5/1/92 7-3. Typical Illustration of High Delta. Trip 5/1/92 7-4. Design to Achieve Isolation Between Channels 7-5. Engineered Safeguards Test Cabinet-Index, Notes and Legend 5/1/92 7-6. Logic Diagram Nuclear Servi W%r :iystem 5/1/92 7-7. Logic Diagram Component Cooling Water System 5/1/92 7-8. Logic Diagram Chemical and Volume Control System 5/1/92 7-9. Logic Diagram Residual Heat Removal System 7-10. Deleted Per 1996 Update 7-11. Deleted Per 1996 Update 5/1/92 7-12. Logic Diagram - Annultis Vent System 5/1/92 7-13. Dom Monitoring Zones 5/1/92 7-14. Logic D;agram - Lower Inlet L. 'ts 4/15/99 7-15. Logic '>iagram: Lower Inlet Doors, Personnel Access Doors, Equip:aent Access Doors and Equipment Access Personnel Doors 5/1/92 7-16. Logie Diagram: Equipment Access and Equipment Access Personnel m Doors

( ) 5/1/92 7-17. Ice Conder ser RTD Location 5/1/92 7-18. Block Diagram: Ice Condenser Temperature Monitoring System 4/15/99 7-19. Containment Pressure Control System Logic 5/1/92 7-20. Reactor Coolant System Overpressure Protection - Train A 5/1/92 7-21. Simplified Block Diagram of Reactor Control System 5/1/92 7-22. Control Bank Rod Insertion Monitor 5/1/92 7-23. Block Diagram of Pressurizer Level Control System 5/1/92 7-24. Block Diagram of Steam Generator Water Level Control System 5/1/92 7-25. Block Diagram of Main Feedwater Pump Speed Control System 4/15/99 7-26. Block Diagrams of Steam Dump Control System 5/1/92 7-27. Basic Flux-Mapping System 7-28. Deleted Per 1996 Update.

1/1/98 7-29. Control Room Layout 4/15/99 7-30. Rod Deviation Comparator 4/15/99 7 31. Block Diagram of Pressurizer Pressure Control System Chapter 8 Figures 4/15/99 8-1. Site Plan of Transmission Lines 4/15/99 8-2. Bulk Power Transmission Network 8-3. Single Line Diagram Typical Auxiliary Distribution System 5/1/92 8-4. Electrical Power System Symbol Legend 4/15/99 8-5. Plan and Profile of McGuire-Harrisburg 230 kV Transmission Lines 8-6. Plan and Profile of McGuire-Harrisburg 230 kV Transmission Lines

-m 4/15/99 8-7. Plan and Profile of McGuire-Riverbend 230 kV Transmission

( ; Lines V 4/15/99 8-8. Plan and Profile of McGuire-Plant Marshall 230 kV Transmission 1999 Update

,,mg Line

! ) 1/12/95 5-9. Plan and Profile of McGuire-Longview 230 kV Transmission Line 8-10. McGuire-Cowans Ford 230 kV Transmission Line 8-11. McGuire-Cowans Ford 230 kV Transmission Line 8-12. Plan and Profile of McGuire-Pleasant Garden 525 kV Transmission Line 4/15/99 8-13. Plan and Profile of Oconee-McGuire 525 kV Transmission Line 8-14. Plan and Profile of Newport-McGuire 525 kV Transmission Line 5/14/96 8-15. Plan and Profile of McGuire-Appalachian 525 kV Transmission Line 4/15/99 8-16. One Line Diagram Station Main Buses (3 parts) 4/15/99 8-17. One Line Diagam Station Main Buses - pages 1 and 2 1/12/95 8-17. One Line Diagram Staticn Main Buses - page 3 4/15/99 8-18. Plan View of Transmission Lines Between Plant and Switching Station 4/15/99 8-19. Primary Relaying Tripping Zones and Protective Relay Zones 5/14/96 8-10. Stability Test Diagram 8-21. Deleted Per 1999 Update 8-22. Deleted Per 1999 Update 8-23. Deleted Per 1999 Update 8-24. Deleted Per 1999 Update l 8-25. Deleted Per 1999 Update l 8-26. Deleted Per 1999 Update 8-27. Deleted Per 1999 Update 4/15/99 8-28. Outside View Reactor Containment Electrical Penetration (m'

Arrangement From Azimuth 270G to 90G 8-29. Outside View Reactor Containment Electrical Penetration Arrangement From Azimuth 90& to 270G 8-30. Computer Simulation of Sequential Loading of Emergency Diesel Generator Under LOCA with Blackout Conditions ;

4/15/99 8-31. Zone G Electrical Protective Relayi,g i 8-32. Diesel Generator Modeling Program Verification Curves 8-33. Single Line Diagram - 250 VDC Auxiliary Power System and Switchyard 125 VDC System 4/15/99 8-34. Single Line Diagram - 125 VDC and 240/120 VAC Auxiliary Control Power Systems 8-35. Vital Instrument and Control Power System (EPG) 8-36. Single Line Diagram 125 VDC/120 VAC Vital Instrument and Control Power System 5/14/96 8-37. 250 VDC Auxiliary Power System Battery Duty Cycle 5/14/96 8-38.125 VDC Auxiliary Control Power System Battery Duty Cycle 1/1/98 8-39.125 VDC Vital Instrumentation and Control System Battery Duty ,

Cycle Chapter 9 Figures 5/14/96 9-1. Fuel Building - General Arrangement 9-2. Fuel Building Section 5/1/92 9 3. Cask Drop Evaluation ( 3 parts) 5/1/92 9-4. Cask Drop Evaluation 5/1/92 9-5. Tornado Missile Study

,% 5/1/92 9-6. Srent Fuel Pool Arrangement Unit 1 2/15/99 9-7. Spent Fuel Pool Arrangement Unit 2 (V) 9-8. Deleted Per 1996 Update 1999 Update

y; , ,

y1 l

[

g

( J 5/l'/92 I 9-9. Fuel Storage Rack Assembly (Region 1) 4[' j 5/1/92 9-10J Fuel Storage Rack Module (Region 2) -

5/1192: ' 9-1li Region 1 Cell Layout ~

5/1/92 E ~ 9-12. Region 2 Cell Layout "4/15/99 9-13. Spent Fuel Cooling System 1/12B5l 9-14. Reactor Manipulator Crane 1/12/95. . 915. Reactor Manipulator Crane '

1/12/95' L 9-16.' Fuel Pool Manipulator Crane )

c9-17. New Fuel Elevator -

-2/15/99 ,9-18.' Fuel Transfer System .

9-19. Rod Cluster Control Changing Fixture 9-20. Spacer for Spent Fuel Storage :

19-21. Reactor Vessel Head Lifting Device .

22. Reactor internals Lifting Device 9-23. Reactor Vessel Stud Tensioner 9-24. ' Auxiliary and Reactor Building Refueling Canal Layout / Longitudinal

Section

'5/14/96 9-25, Flow Diagram of Recirculated Cooling Water System 2/1569 9-26. Flow Diagram of Recirculated Cooling Water System l 2/15/99 9-27. Recirculated Cooling Water System -

l 12/1569 19-28. Recirculated Cooling Water System

^

. 4/1/98 9-29 Flow Diagram of Recirculated Cooling Water System 4/15/99f_- -- 9-30. Flow Diagram of Recirculated Cooling Water System

.2/15B9 9-31. Nuclear Service Water System 9 32. Deleted Per 1993 Update

9-33f Deleted Per 1993 Update, j

-- 9-34l Deleted Per 1993 Update 35; Deleted Per 1993 Update ~

9-36. Deleted Per 1993 Update 9-37.' Deleted Per 1993 Update l

~ 9 38. Deleted Per 1991 Update

.5/14/96 9-39. Residual Decay Heat - !

Y :5/14/96 l 9-40. Residual Decay Heat

'5/14/96. 9-41. Total Heat Rejected 5/1/92: 9-42. Standby Nuclear Service Water Pond Area / Volume Curve 9-43. Low Level Nuclear Service Water Pipe and Standby Nuclear Service

. Water Pipe Routing Plan . .

9-44. Profile of Standby Nuclear Service Water Pipes 9-45. Profile of Low Level Nuclear Service Water Pipe

'2/15S9- 9-46. Nuclear Service Water System Piping Layout 2/15/99- 9-47. Nuclear Service Water System Piping Layout 9-48. Nuclear Service Water System Piping Layout 2/15/99 9-49. Nuclear Service Water System Piping Layout 2/1569L

50. Nuclear Service Water System Piping Layout i, - 2/15/99 : ~ 9-51.~ Nuclear Service Water System Piping Layout

' 9-52. Nuclear Service Water System Piping Layout 9-53. Nuclear Service Water System Piping Layout 4/1569 . 9-54) Flow Diagram of Conventional Low Pressure Service Water System

. ' (RL)

L 4/168 - " 9-55. Flow Diagram of Conventional Low Pressure Water System (RL)

' (Service Bldg. Cooling Coils)

'4/1589. 9-56. Conventional Low Pressure Service Water System (RL) 2/15/99- 9-57. Component Cooling System K).

7 Di 9-58. Deleted Per 1996 Update 9-59. Deleted Per 1996 Update 1999. Update

P ,

9-60. Deleted Per 1996 Update fw 9-61. Deleted Per 1996 Update D 9-62. Deleted Per 1996 Update -

9-63. Deleted Per 1996 Update L 9-64. Deleted Per 1996 Update I

' 2/15/99 ' 9-65. Flow Diagram of Refueling Water System -

2/15S9- 9-66. Flow Diagram of Filtered Water System -

3 4/1/98' 9-67. Flow Diagram of Filtered Water System . 1 4/1/98 9-68.' Flow Diagram of Filtered Water System (YF)

'l 4/1/98 9-69 Flow Diagram of Makeup Demineralized Water System (YM) 4/188 , 9-70. Flow Diagram of Makeup Demineralized Water System

]

4/198 71. Flow Diagram of Makeup Demineralized Water System 1 2/1569 9-72.' Flow Diagram of Makeup Demineralized Water System 4/1/98 9-73. Makeup Demineralized Water System (YM) 4/15 S 9 - 9-74. Makeup Demineralized Water System' .

-2/1569 9-75. Flow Diagram of Makeup Demineralized Water System - i

' 4/1/98 9-76. Flow Diagram of Drinking Water System l

,- 2/15/99 9-77. Flow Diagram of Conventional Waste Water Treatment System l 9-78. Deleted Per 1993 Update 1 4/15/99 9-79. Flow Diagram ofInstrument Air System l 80.' Deleted Per 1993 Update 9-81. Deleted Per 1993 Update l 9-82. Deleted Per 1993 Update 1

9/163-' 9-83. Flow Diagram of Station Air System 9-84. Deleted Per 1993 Update 9-85. Deleted Per 1993 Update y 9-86. Deleted Per 1993 Update y ._ _ 9-87. ' Deleted Per 1993 Update -

'9-88. Deleted Per 1993 Update ls . 9-89. Deleted Per 1993 Update 2/15/99 - , 9-90. Nuclear Sampling System (hM) s 2/15/99 9 91. Flow Diagram of Nuclear Sampli:.g System

-2/15/99 9-92. Flow Diagram of Nuclear Sampling System

' 9-93. Deleted Per 1996 Update 9-94. Deleted Per 1993 Update 9-95. Deleted Per 1993 Update

-2/1569 9-96.' Flow Diagram of Chemical and Volume Control System 9-97. Deleted Per 1993 Update

-2/1569- 9-98. Flow Diagram of Chernical and Volume Control System 9-99. Deleted Per 1993 Update 9-100. Deleted Per 1993 Update 9-101. Deleted Per 1993 Update

( 9-102. Deleted Per 1993 Update I .-

19-103. Deleted Per 1993 Update 9-104. Pc'-ted Per 1993 Updste 105. b icted Per 1993 Update 9-106. Deleted Pet 1993 Update 9-107. Flow Diagram of Boron Thermal Regeneration System

' 9-108. Flow Diagram of Boron Thermal Regeneration System 9-109.- Flow Diagram of Boron Thermal Regeneration System 2/1569 9-110. Flow Diagram of Boron Recycle System (hT)

- 9-111. Deleted Per 1994 Update l 9-112. Deleted Per 1994 Update u

']t' n 9-113. Deleted Per 1994 Update 9-114.. Deleted Per 1994 Update 1999 Update i, ..

i

. o/T 9115 Deleted Per 1994 Update ;

{F -

j2/15S9 L 9-116. Post Accident Liquid Sampic System 9-117. Flow Diagram of Auxiliary Building Ventilation System 2/15/99, ' 9-118.' Flow Diagram of Auxiliary Building Ventilation System l

4/15/99 ' 9-119. Flow Diagram of Auxiliary Building Ventilation System - page 1 9/183' L. -

9-119; Flow Diagram of Auxiliary Building Ventilation System-page 2 4/168 ' 9-120. Flow Diagram of Turbine Building Ventilation System 2/15/99. ' 9-121.' Flow Diagram of Containment Purge and Ventilation System 9-122. Deleted Per 1994 Update >

> 5/14/96 ' 123. Flow Diagram of Diesel Building Ventilation System -

2/15/99 9-124. Fire Protection System :

9/1/93 __9-125.' Flow Diagram of Fire Protection System 9126. Deleted Per 1993 Update r

9-127i Deleted Per 1993 Update -

' 9-128. Deleted Per 1993 Update .

' 9-129. Deleted Per 1993 Update-t 9-130. Deleted Per 1993 Update 9-131; Deleted Per 1993 Update 2/1569 9-132. Communication Systems -

2/15/99 9-133, Communication Systems

2/15/99 - 9-134.; Communication Systems 9-13S. Communication Systems 2/15 S 9 9-136. Communication Systems 2/15/99 . 9-137.' Communication Systems 2/15S9 M3E Communication Systems .

2/15/99 9-139. Summary Flow Diagram of Diesel Generator Engine Fuel Oil System n .

9140. Deleted Per 1993 Updatei 2/15/99 i 9-141. Flow Diagram of Diesel Generator Engine Cooling Water System .

9-142. Deleted Per 1993 Update -

4/15/99 9143. Diesel Generator Engine Starting Air System 2/15/99. 9-144. Flow Diagram of Diesel Generator Engine Lube Oil System 9-145. Deleted Per 1993 Update

2/15B9 9-146. Groundwater Drainage System 2/15/99 9-147. Flow Diagram of Diesel Generator Engine Crankcase Vacuum System 2/15/99 9-148. Flow Diagram of Diesel Generator Room Sump Pump System

2/1569 149. Flow Diagram of Diesel Generator Engine Air intake & Exhaust System 4/1569 150. Containment Air Release and Addition S;stem Chapter 10 Figures 4/1569' 10-1. Heat Balance (Guaranteed) 4/1569 10-2. Heat Balance (Valves Wide Open) 4/15/99 10-3. Flow Diagram of Moisture Separator Reheater Bleed System 4/15/99 10-4. Flow Diagram of Moisture Separator Reheater Bleed Steam System

- (HM) Heater Bleed Steam System (HA & HB) Turbine Crossover System (SC) 5/14/96- 10-5. Flow Diagram of Heater Bleed Steam System 5 9 /96 ;10-6. Flow Diagram of Heater Bleed Steam System 5/14/96- 10-7. Flow Diagram of Heater Bleed Steam System 5/1466 10-8. Flow Diagram of Heater Bleed Steam System 5/14/96 10-9. Flow Diagram of Heater Bleed Steam System j fy

t i 4/15/99l 2/15/99 10-10. Turbine Overspeed Control 10-11. Flow Diagram of Main Steam Supply to Auxiliary Equipment System Turbine Exhaust

i

}

1999 Update s .

i

I 10-12. Deleted Per 1994 Update p/

i 2/15/99 10-13. Flow Diagram Main Steam Supply to Aux. Equipment System (SA)

Turbine Exhaust (TE) 10-14. Deleted Per 1994 Update 10-15. Deleted Per 1994 Update 4/1/98 10-16. Flow Diagram of Steam Supply to FDWP Turbine System (SP) Turbine Exhaust System (TE) Moisture Sep. Reheater Bleed Stm. System (HM) 4/1/98 10-17. Flow Diagram of Main Steam Bypass to Condenser System (SB) 4/1/98 1018. Flow Diagram of Main Condenser l A Connections Condensate System 4/1/98 10-19. Flow Diagram of Main Condenser IB Connections Condensate System 4/1/98 10-20. Flow Diagram of Main Condenser 1C Connections Condensate System 4/1/98 10-21. Flow Diagram of FDW Pump Turbine Condenser I A & 1B Connections 5/14/96 10-22. Flow Diagram of Main Vacuum System 4/1/98 10-23. Flow Diagram of Vacuum Priming System 4/15/99 10-24. Flow Diagram of C.S.A.E. System 5/14/96 10-25. Flow Diagram of Condenser Steam Air Ejector System 2/15/99 10-26. Flow Diagram of Main Turbine Leakoff and Steam Seal System 4/1/98 10-27. Flow Diarram of FDW Pump Turbine Steam Seal System 4/1/98 10-28. Flow Diagram of Condenser Circulating Water System 4/1/98 10-29. Flow Diagram of Low Level Intake Cooling Water System 10-30. Deleted Per 1996 Update N 10-31. Deleted Per 1996 Update (j

i 10-32. Deleted Per 1996 Update 10-33. Deleted Per 1996 Update 10-34. 'eleted Per 1996 Update .

10-35. Cu., denser Cooling Water Intake Structure General Arrangement Plan and Sections 10-36. Condenser Cooling Water Low Level Pump Structure Concrete and Miscellaneous Steel Plan and Sections 2/15/99 10-37. McGuire Nuclear Station Unit 1 Flow Diagram of Condensate System (CM) 4/1/98 10-38. Flow Diagram of Condensate System 4/1/98 10-39. Flow Diagram of Condensate System 4/1/98 10-40. Flow Diagram of Condensate System 2/15/99 10-41. Flow Diagram of Condensate System 4/1/98 10-42. Flow Diagram of Condensate System 2/15/99 10-43. Flow Diagram of Condensate System - page 1 5/14/96 10-43. Flow Diagram of Condensate System - page 2 2/15/99 1044. Flow Diagram of Condensate Storage System (CS) 2/15/99 10-45. Flow Diagram of Main Feedwater System 10-46. Deleted Per 1993 Update 4/15/99 10-47. Flow Diagram of Auxiliary Feedwater System 10-48. Deleted Per 1993 Update 4/15/99 10-49. General Piping Layout Feedwater System 4/15/99 10-50. General Piping Layout Auxiliary Feedwater System 2/15/99 10-51. Flow Diagram of Steam Generator Blowdown Recycle System (BB) 10-52. Deleted Per 1994 Update

,f-] 10-53. Deleted Per 1994 Update i i 4/1/98 10-54. Flow Diagram of Heater Drain System

2/15/99 10-55. McGuire Nuclear Station Unit 1 Flow Diagram of Heater Drain System 1999 Update

a j-

. 4/1/98 10-56. Flow Diagram of Heater Drain System -

'4/1569 10-57. Flow Diagram of Heater Drain System 2/15/99L 10-58. Flow Diagram of Moisture Separator Reheater Drain System 2/1569. 10-59. Flow Diagram of Moisture Separator Reheater Drain System 12/15/99 ~ 10-60. Flow Diagram of Moisture Separator Reheater Drain System 2/15S91 ; 10-61. Flow Diagram of Moisture Separator Reheater Drain System

' 2/15/99.. ~ 10-62. Flow Diagram of Moisture Separator Reheater Drain System-

-2/15/99> 10-63. Flow Diagram of Moisture Separator Reheater Drain System l

Chapter 11 Figures 4/1/98' Il-1. Flow Diagram of Liquid Waste Recycle System

^ l12. Deleted Per 1993 Update . !

11-3. Deleted Per 1993 Update

~11-4. Deleted Per 1993 Update l

.11-5. Deleted Per 1993 Update ,

.116.' Deleted Per 1993 Update !

11-7 Deleted Per 1993 Update i 11-8. Deleted Per 1993 Update

. Il-9. Deleted Per 1993 Update

' 11-10. Deleted Per 1993 Update 4/1/98 ;Il-11. Flow Diagram of Equipment Decontamination System

11 12. Deleted Per 1993 Update 11-13. Deleted Per 1993 Update

, 11-14.- Average Equilibrium Concentrations of Radionuclides in Lake Norman 9/1/93 11-15. Flow Diagram of Waste Gas System O 9/1/93 11-16. Deleted Per 1993 Update :

11 17. Deleted Per 1993 Update

' 11-18.' Flow Diagram of Waste Gas System I

i1-19. Deleted Per 1993 Update 1120. Deleted Per 1993 Update

< 5/1/92 1121. Estimated Waste Gas System Fission Gas Accumulation Based on Continuous Core Operation at 3580 MWt with 1 Percent Fuel

i. ' Defects .

4/15/99: . I1-22. Flow Diagram of Nuclear Solid Waste Disposal System j 1123. Deleted Per 1999 Update 11-24. Deleted Per 1996 Update '

Il-25. Deleted Per 1996 Update 1126. Radiological Sampling Stations

_ Chapter 12 Figures 5/182 121. Radiation Zones at El. 695 + 0 5/1/92- 12-2. Radiation Zones at El. 716 + 0 =

5/1/92 ' 12-3. Radiation Zones at El. 733 + 0 and 739 + 0

.. i5/162 12-4. Radiation Zones at El 750 + 0 1:

~

5/1/92~ .12-5. Radiation Zones at El. 760 + 6 and 767 + 0

' 5/1/92 - 12-6; Radiation Zones at El. 786 + 0

- 5/1/92- 12-7. Radiation Zones Longitudinal Section 5/1/92 ~ 12-8. Control Room Isometric Chapter 13 Figures 1/12/95.- 13-L Corporate Organization 1/188 13-2. Power Ceneration Group Organization Chart 2/15/99. 13-3. Nuclear Generation Department t-1999 Update

r ,

i l

1 jN 1/1265 134 Typical Nuclear Site Organization f 13-5. Deleted Per 1994 Update

)- 13-6. Deleted Per 1992 Update 13-7. Deleted Per 1992 Update 5/1/92 13-8. "At the Controls" Defm' ition - l Chapter 14 Figures 3/1/92' 141.. SpecialTestInstrumentation i 5/1/92

' 14-2. Piezo Transducer Fixture Installation in Preheater -

5/1/92/ 14-3, Piezoelectric Transducer Probe in Feedline Check Valve Chapter 15 Figures

'1/12/95 - 15.-l.' Illustration of Overtemperature and Overpower & Delta.T Protection

.15-2. Deleted per 1998 Update 15-3. Deleted per 1998 Update 15-4. Deleted per 1998 Update 15-5. Deleted per 1998 Update' 15-6. Dleeted per 1998 Update i 1/1/98- 15-7. Excessive Increase in Feedwater Flow 1/1/98 15-8. Excessive Increase in Feedwater Flow 1/1/98- 15-9. Ten Percent Step Load Increase, Minimum Reactivity Feedback, Manual Reactor Control i 1/1/98 15-10. Ten Percent Step Load Increase, Minimum Reactivity Feedback, l Manual Reactor Control 1/1/98 15-11. Ten Percent Step Load Increase, Maximum Reactivity Feedback, Manual Reactor Control

[m]

'\ -

1/1/98 15-12.' Ten Percent Step Load Increase, Maximum Reactivity Feedback, Manual Reactor Control 15-13. Deleted per M98 Update 4

15-14. Deleted per 1998 Update ,

.15-15. Deleted per 1998 Update l 15-16. Deleted per 1998 Update 1/1/98 ~ 15-17. K-effective Versus Moderator Temperature for Valve Opening 1/188 ,15-18. Failure of a Steam Generator Safety or Dump Valve ( 4 parts) 1/1/98 15-19. Failure of a Steam Generator Safety or Dump Valve ( 4 parts) 15-20. Deleted per 1998 Update 1/1/98 15-21. Steamline Break, Offsite Power Maintained .I 1/1/98 15-22. Steamline Break, Offsite Power Maintained i

-1/1/98 23. Steamline Break, Offsite Power Maintained

-1/1/98 15-24. Steamline Break Offsite Power Maintained l 1/1/98 15-25. Steamline Break, Offsite Power Maintained 1/1/98- 15-26. Steamline Break, Offsite Power Maintained 1/1/98 c 15-27. Turbine Trip, Maximum Secondary Pressure Case 1/1/98' 15-28. Turbine Trip, Maximum Secondary Pressure Case -

' 1/1/98 ~- 15-29. Turbine Trip, Maximum Secondary Pressure Case 1/1/98 15-30, Turbine Trip Maximum Secondary Pressure Case 1/1/98 15-31. Turbine Trip, Maximum Secondary Pressure Case ;

1/1/98 15-32. Turbine Trip, Maximum Primary Pressure Case l 1/12/95 33. Feedwater System Pipe Break, Short Term Core Cooling Analysis

/ ,c 1/12/95 ' 15-34.' Feedwater System Pipe Break, Short Term Core Cooling 7

Analysis

!- 1/1/98- 15-35. Loss of Offsite Power ,

1999 Update

P i

I f3 1/1/98 15-36. Loss of Offsite Power

! ( ) .1/1/98 . 15-37. Loss of Offsite Power l '# 1/1/98 15-38. Loss of Normal Feedwater (3 parts) l l

1/168 15-39. Loss of Normal Feedwater ( 2 parts) l I 1/1/98 15-40. Feedwater System Pipe Break, Long Term Core Cooling Analysis 1/1/98 15-41. Feedwater System Pipe Break, Long Term Core Cooling Analysis 1/1/98 15-42. Feedwater System Pipe Break, Long Term Core Cooling Analysis l 1/1/98 15-43. Feedwater System Pipe Break, Long Term Core Cooling Analysis l 1/1S8 l 15-44. Feedwater System Pipe Break, Long Term Core Cooling Analysis l- ' 1/IS8 15-45. Feedwater System Pipe Break, Long Term Core Cooling Analysis 1/1S8 15-46. Feedwater System Pipe Break, Long Term Core Cooling Analysis l 15-47. Deleted Per 1992 Update I l

15-48. Deleted Per 1992 Update 15-49. Deleted Per 1992 Update 15-50. Deleted Per 1992 Update 4/15/99 15-51. Partial Loss of Forced Reactor Coolant Flow 4/15/99' 15-52. Partial Loss of Forced Reactor Coolant Flow 4/15S9 15-53. Partial Loss of Forced Reactor Coolant Flow i 4/15/99 15-54. Partial Loss of Forced Reactor Coolant Flow 4/15/99 15-55. Partial Loss of Forced Reactor Coolant Flow i

5/1/92 15-56. Complete Loss of Forced Reactor Coolant Flow 5/1/92_ 15-57. Complete Loss of Forced Reactor Coolant Flow 5/162 15-58. Complete Loss of Forced Reactor Coolant Flow 5/1S2 15-59. Complete Loss of Forced Reactor Coolant Flow 5/1/92 15-60. Complete Loss of Forced Reactor Coolant Flow 5/14/96 15-61. Complete Loss of Forced Reactor Coolant Flow et 1/168 15-62. Locked Rotor RCS Flow (Fraction ofInitial)

( ) 1/12/95 15-63. Uncontrolled RCCA Bank Withdrawal at HZP V 1/12/95 15-64. Uncontrolled RCCA Bank Withdrawal at HZP 1/12/95 15-65. Uncontrolled RCCA Bank Withdrawal at HZP 1/12/95 15-66. Uncontrolled RCCA Bank Withdrawal at HZP 1/12/95 15-67. Uncontrolled RCCA Bank Withdrawal at HZP 1/12/95 15-68. Uncontrolled RCCA Bank Withdrawal at HZP 5/162 15-69. Uncontrolled RCCA Bank Withdrawal from 10% Power 5/162 15-70. Uncontrolled RCCA Bank Withdrawal from 10% Power 5/1/92 15-71. Uncontrolled RCCA Bank Withdrawal from 10% Power 5/1/92 15-72. Uncontrolled RCCA Bank Withdrawal from 10% Power 5/1/92 15-73. Uncontrolled RCCA Bank Withdrawal from 10% Power 5/1/92 15-74. Uncontrolled RCCA Bank Withdrawal from 50% Power 5/1/92 15-75. Uncontrolled RCCA Bank Withdrawal from 100% Power 5/1/92 15 76. Single RCCA Withdrawal 1/1/98 _15-77. Improper Startup of an Inactive Reactor Coolant Pump 1/1/98 15-78. Improper Startup of an inactive Reactor Coolant Pump 1/1/98 15 79. Improper Startup of an Inactive Reactor Coolant Pump ,

1/1/98 15-80. Improper Startup of an Inactive Reactor Coolant Pump l 1/1/98 15-81. Improper Startup of an inactive Reactor Coolant Pump 5/1/92 15-82. Interchange Between Region 1 and Region 3 Assembly 5/1/92 15-83. Interchange Between Region 1 and Region 2 Assembly, Burnable Poison Rods Being Retained by the Region 2 Assembly

! 5/1/92 15-84. Interchange Between Region 1 and Region 2 Assembly, Burnable Poison Rods Being Transferred to the Region 1 Assembly 5/1/92 15-85. Enrichment Error: A Region 2 Assembly Loaded into the Core n Central Position 5/1/92 15-86. Loading a Region 2 Assembly into a Region 1 Position Near Core (V) Periphery l 1999 Update e

W' .w -

a - ,

.e 1y g

5/1/92;

, 5/1/92 '15-87i Single RCCA Withdrawal s15-88T Single RCCA Withdrawal' i 9/1/93 : 15-89.' Single RCCA Withdrawal '

is 1/1/98 15-90. Dropped Rod Accident 15-91.' Deleted per 1998 Update R

~

15-92.' Deleted per 1998. Update 1/1265 15-93. Inadvertent Actuation of ECCS During Power Operation -

1/168 ! 15-94. Inadvertent OpeningM a Pressurizer Safety Valve -

'1/168* : 15-95. Inadvertent Opening of a Pressurizer Safety Valve -

? l5-96. Deleted per 1998 Update T "i 4/15/99 '15-97. Sequence of Events for Large Break Loss-of-Coolant Analysis L 15-98.' Deleted Per 1996 Update 15-99. Deleted per 1998 Update..15-100.Through 15-132 Deleted Per 1996 Update -

1/1265 . i 15-133. Compartment Pressure, Min SI

'15-134. Deleted per 1998 Update 15-135. Deleted Per 1996 Update 136. Deleted Per 1996 Update '

1/1/98 : 15-137. Small Break Power Distribution Assumed for LOCA Analysis15-138. Deleted per 1998 Update

= 1/12/95 15-139. Safety injection Flowrate vs. Pressure, Small Break 15-140.Through 15151 Deleted per 1998 Update 15-152. Deleted Per 1994 Update s

~ 15-153. Deleted Per 1994 Update -

4/15/99 : 15-154. RCCA Position Versus Time to Dashpot 5/1/92- : 15-155. Normalized Rod Worth Versus Percent Inserted

.- 4/15/99 ;15-156. Normalized RCCA Bank Reactivity Worth Versus Normalized Drop

- sg ..

1/1/98 '

. Time .15-157 Steamline Break Offsite Power Maintained

'l/1/98 '15-158. Steamline Break Offsite Power Main.tained J

- 1/1/98 - 15-159. Steamline Break Offsite Power Maintained -

t 1/1/98 15-160. Steamline Break Offsite Power Maintained 1/1/98 ~ 15-161. Steamline Break Offsite Power Maintained

,1/1/98 .15-162. Steamline Break Offsite Power Lost 1/1/98'15-163. Steamline Break Offsite Power Lost

-1/1/98 15-164. Steamline Break Offsite Power Lost

1/1/98 15-165. Steamline Break Offsite Power Lost 1/1/98 .15-166. Steamline Break Offsite Power Lost 1/1/98 - 15-167. Steamline Break Offsite Power Lost 1/1/98: 15-168. Steamline Break Offsite Power Lost l . 11/1/98 c 15-169. Steamline Break Offsite Power Lost h ' 1/1/98 : 15-170. Steamline Break Offsite Power Lost "1/1/98 15-171. Steamline Break Offsite Power Lost -

1/1/98 15-172. Steamline Break Offsite Power Lost 15-173. Deleted per 1998 Update

! 1 1/1/98 15-174. Locked Rotor Neutron Power (% of Nominal)

L , '1/1/98 '15-175. Locked Rotor Core Average Heat Flux (Fraction of Nominal) q l' 1/1/98 15-176. Locked Rotor Loop Average Temperature (Deg F) ;

1/1/98 15177 Locked Rotor Pressurizer Pressure (psig) 5/1/92 15-178. Locked Rotor RCS Pressure (psig) 15179. Deleted per 1998 Update i1/1/98.15-180. Dropped Rod Accident --

7% l 5/1/92' 5/1/92 15181. Dropped Rod Accident

.15-182. Dropped Rod Accident 5/1/92 15-183. Dropped Rod Accident l '

i 1999 Update 4

r i

^

s 1/1/98 15-184. Rod Ejection Accident (BOC,HFP)

( "

) 1/1/98 15-185. Rod Ejection Accident (EOC,HZP) 9/1/93 15-186. Uncontrolled RCCA Bank Withdrawal at HZP Max. NC Pressure PSig 5/1/92 15-187. Uncontrolled RCCA Bank Withdrawal @ 10% Power Pressure (psia) 1/1/98 15-188. RSG LBLOCA EM Revision 3 Computer Code Interface 15-189. Deleted per 1998 Update 15-190. Deleted per 1998 Update 15-191. Deleted per 1998 Update 1/1'98 15-192. LBLOCA,9.7 ft. Peak, Reflooding Rate-Core Entrance Location 1/1/98 15-193. LBLOCA,9. 7 ft. Peak HC Quench Front & Collapsed Liquid Level 1/1/98 15-194. LELOCA,9.7 ft. Peak , Cladding Temperature 1/1/98 15-195. LBLOCA ,9.7 ft. Peak, HC Local Oxidation 1/1/98 15-196. LBLOCA,9.7 ft. Peak, Hot Channel Fuild Temperatur, 8.6 Elevation 1/1/98 15-197. LBLOCA,9.7 ft. Peak, Downcomer Water Level 1/1/98 15-198. LBLOCA,9.7 ft. Peak, ECCS Flow 15-199. Deleted per 1998 Update 15-200. Deleted per 1998 Update 15-201. Deleted per 1998 Update 5/14/96 15-202. RELAPS Large Break LOCA Loop Noding Model 5/14/96 15-203. RELAPS/ BEACH Large Break LOCA Reactor Vessel Noding Model 5/14/96 15-204. REFLOD3B Large Break LOCA Noding Model 15-205. Deleted Per 1996 Update 15-206. Deleted Per 1996 Update 1/1/98 15-207. Excessive incense in Feedwater Flow

/~ 1/1/98 15-208. Excessive Increase in Feedwater Flow (N'~) 1/1/98 1/1/98 15-209. Excessive Increase in Feedwater Flow 15-210. Excessive Increase in Feedwater Flow 15-211. Deleted per 1998 Update 1/1/98 15-212. Loss of Offsite Power 1/1/98 15-213. Loss of Offsite Power 1/1/98 15-214. RELAP5/ MOD 2 - B & W SBLOCA Primary Loop Nodalization 1/1/98 15-215. RELAP5/ MOD 2 - B & W SBLOCA Reactor Vessel Nodalization 1/1/98 15 216. SBLOCA,2.5 Inch Break, RCS Pressure 1/1/98 15-217. SBLOCA,2.5 Inch Break, Break Flow Rate 1/1/98 15-218. SBLOCA,2.5 Inch Break, Hot Channel Froth and Collapsed Level 1/1/98 15-219. SBLOCA,2.5 Inch Break, Cladding Temperature PCT Location 1/1/98 15-220. SBLOCA,2.5 Inch Break, Vapor Temperature at PCT Location 1/1/98 15-221. SBLOCA,3 Inch Break, RCS Pressure 1/1/98 15-222. SBLOCA,3 Inch Break, Break Flow Rate 1/1/98 15-223. SBLOCA,3 Inch Break, Hot Channel Froth and Co lapsed Level 1/1/98 15-224. SBLOCA,3 Inch Break, Cladding Temperature PCT Location 1/1/98 15-225. SBLOCA,3 Inch Bicai, Vapor Temperature at PCT Location 1/1/98 15-226. Steam Generator Tube Rupture 1/1/98 15-227. Steam Generator Tube Rupture 1/1/98 15-228. Steam Generator Tube Rupture 1/1/98 15-229. Steam Generator Tube Rupture 1/1/98 15-230. Steam Generator Tube Rupture 1/1/98 15-231. Steam Generator Tube Rupture 1/1/98 15-232. Steam Generator Tube Ruptuse l

t f-f I wJ 1999 Update

ML20217H581

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