Text

Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Figure 4.25 - Case 3 Through Calculation PCI-5464-S01, Page 107
	ML081090502
Person / Time
Site:	Watts Bar
Issue date:	03/31/2008
From:	Brandon M K; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
References
	GL-04-002, TAC MC4730 PCI-5464-S01, Rev 2
	Download: ML081090502 (267)
	v • d • e

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation tI 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-26 of 4-53 SCIIfcle , 0,o DouetNtO M==tl- iit ýO~ D"" f l~d~~ec"W 00 ¶-M1 44*c.40 V*.WI04*Ooo Figure 4.25 Case 3 -Steel Subtracted from IOD ZOI Sphere Within 6' of Floor

] Watts Bar Reactor Building GSI- 191 Debris Generation Calculation tF / I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-27 of 4-53.Ntxl u Figure 4.26 -Case 3 -Steel Intersected with I OD ZOI Sphere Within 6' of Floor 9 Watts Bar Reactor Building GSI-191 Debris Generation Calculation A/ O L Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-28 of 4-53 Figure 4.27 -Case 4 -Concrete Subtracted from 1 OD ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation I 0 N Document No:ALION-CAL-TVA-2739-03 I Rev:3 Page: 4-29 of 4-53 sclcf. DEWO o cuetNoLO Figure 4.28 -Case 4 -Concrete Intersected with 1 OD ZOI Sphere

Watts Bar Reactor Building GSI-191 Debris Generation CalculationL I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-30 of 4-53 (MCI tc! or, tDCWtOLOot Figure 4.29 -Case 4 -Steel Subtracted from I OD ZOI Sphere

Watts Bar Reactor Building GSI-191 Debris Generation Calculation..o o"O ' Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-31 of 4-53 tara Pas 49 OW, ~d 101,60 *11I n (12 4 q-u. ft 1 stt.4' cc..i.Figure 4.30 -Case 4 -Steel Intersected with I OD ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation A, I9c, O ,N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-32 of 4-53~otflm PmAt ~)V*d4J'~4U.Ct 3 I leak, 0 a ^ftftaw:-ý I 4 Figure 4.31 -Case 4 -Concrete Subtracted from I OD ZOI Sphere Within 6' of Floor 0 Watts Bar Reactor Building GSI- 191 Debris Generation CalculationAN* 0t..0°0, Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-33 of 4-53 r*rt w all W1.. f13)~/ .~q~ t )ý 0 " O Figure 4.32 -Case 4 -Concrete Intersected with IOD ZOI Sphere Within 6' of Floor

Watts Bar Reactor Building GSI- 191 Debris Generation CalculationtE OLN Document No:ALION-CAL-TVA-2739-03 I Rev:3 Page: 4-34 of 4-53 Figure 4.33 -Case 4 -Steel Subtracted from lOD ZOI Sphere Within 6' of Floor

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation 10, NtC @O Document No:ALION-CAL-TVA-2739-03 I Rev:3 Page: 4-35 of 4-53 Figure 4.34 -Case 4 -Steel Intersected with 1OD ZOI Sphere Within 6' of Floor

Watts Bar Reactor Building GSI-191 Debris Generation CalculationL I N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-36 of 4-53 SC$KCIZ D c e flCL*OLO o miy fti oww poin owObjwct/Add/SUbt~pt 2: a Im~t objects:.1324021-S9731 squate in. (9194,59442S8 sqv.ýe ft I. Feit=st.-o WO*ao Figure 4.35 -Case 1 -Steam Generators Subtracted from IOD ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation st .. I 0 OG' Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-37 of 4-53 P~vr o~~tortObject/Odd49tract]

a 42926 oqwwo ýn (20.539 squAe ft.). Pe~rxct=-A Figure 4.36 -Case I -Steam Generators Intersected with 1 OD ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation L I ON Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-38 of 4-53 scitpcl AN* TtC 0 DuLO m 75592 wu In (68596.6371931 wut ft.). PýI6~t=-1 Figure 4.37 -28.6D ZOI Sphere

Watts Bar Reactor Building GSI-191 Debris Generation Calculation

%t L I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-39 of 4-53 Ij 2907 qu- "- (74079 6156596 q..- ftý), P--t- -Figure 4.38 -Case 1 -Equipment Subtracted from 28.6D ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation A,.. I O N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-40 of 4-53 t Yob~ects--87139949171 q e Xm , (6051 3053591 sqý it Per-t=00000 Figure 4.39 -Case I -Equipment Intersected with 28.6D ZOI Sphere

Watts Bar Reactor Building GSI-191 Debris Generation Calculation I ON Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-41 of 4-53 SCatO.O M". 0, D c mnLOI Figure 4.40 -Case 2 -Steam Generators Subtracted from 1 OD ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation CalculationcI 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-42 of 4-53 corter poxot or (Object/Add/Subtraot]

o Figure 4.41 -Case 2 -Steam Generators Intersected with I OD ZOI Sphere

Watts Bar Reactor Building GSI-191 Debris Generation Calculation L I ON Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-43 of 4-53 s *tc g I-00 DiKO o cmn oLO 17116 q-- (75406.9109108

-ft.), Pori-t-Figure 4.42 -Case 2 -Equipment Subtracted from 28.6D ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation.I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-44 of 4-53$ .I[ASf9 T1 .0DNOmnOY P93 s (Bi 4841.0912393 .qu"~ ft ).Prxt I Figure 4.43 -Case 2 -Equipment Intersected with 28.6D ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation WI I_ 0 T N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-45 of 4-53.tcnrppiut

= (Object/Add/Subtract]:

o Figure 4.44 -Case 3 -Steam Generators Subtracted from 1 OD ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation AL / I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 f Page: 4-46 of 4-53 ASIEcAN UCH*OtO OGY D c m n o square x.i (1203.9660208 square ft. ). Psrictvz --j Figure 4.45 -Case 3 -Steam Generators Intersected with 1OD ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation 60,.f.k Ec* 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-47 of 4-53 18768 nqý in (7125.0068509 xq" it) ~mt -Figure 4.46 -Case 3 -Equipment Subtracted from 28.6D ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation.I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-48 of 4-53 scigmct 4 LOGY Doumnoto Figure 4.47 -Case 3 -Equipment Intersected with 28.6D ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation AL I O N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-49 of 4-53 313,31611 (9. 189 67S8063 qý ft.). -~-Figure 4.48 -Case 4 -Steam Generators Subtracted from lOD ZOI Sphere

Watts Bar Reactor Building GSI-191 Debris Generation Calculation 6A/ I 10 I Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-50 of 4-53 1733614 i (1203,839309 sqiw.x ft ), Pmiu~t=-0.000on Figure 4.49 -Case 4 -Steam Generators Intersected with I OD ZOI Sphere

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation Wt. I 0 *I Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-51 of 4-53 5890 aqutv* in. ý74106 2193623 squAr. ft.), P-tw -Figure 4.50 -Case 4 -Equipment Subtracted from 28.6D ZOI Sphere

Watts Bar Reactor Building GSI-191 Debris Generation Calculation SE / I c 0 Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-52 of 4-53 Figure 4.51 -Case 4 -Equipment Intersected with 28.6D ZOI Sphere

Watts Bar Reactor Building GSI-191 Debris Generation CalculationI 0N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-53 of 4-53-IcE-0c 14C.. 041 Dm~o cuet oAL Figure 4.52 -Dome Area Projection Over Crane Wall

Watts Bar Reactor Building GSI-191 Debris Generation Calculation N Document No: ALION-CAL-TVA-2739-03 Rev:3 Page: 5-1 of 5-7 APPENDIX 5 -3M WORKSHEETS This Appendix contains the 3M calculation worksheets which were created to analyze shielding for the 3M insulation materials.

Table 5-1 "TVA Walkdown Report / 1-47A243-6-0 Reconciliation" was used to identify and aid in mapping all conduits, raceways and junction boxes listed in "Watts Bar Nuclear Plant Unit No. 1, 3M M20C Radiant Energy Shield 47A243-6-0".

This table displays line items from "'Report on Watts Bar Unit 1 Containment Building Walkdowns for Emergency Sump Strainer Issues', TVAWOO I-RPT-00 1, Rev 0."[Ref.9] and reconciles these items with the actual conduits from 1-47A243-6-0.

The legend for Table 5-1 is as follows: This information is a line item as it is represented in the TVA walkdown report and is a "header" for the following items. For 3M insulation targets, these line items were found to summarize several different conduits, junction boxes or conduit supports into a single line item.Identified I Mapped and analyzed for shielding These items are individual conduits, junction boxes or conduit support entries as they are found in "Watts Bar Nuclear Plant Unit No. 1, 3M M20C Radiant Energy Shield 47A243-6-0".

The individual items are reconciled with the TVA walkdown report and listed under the appropriate line items from that report.Identified I Duplicate target, mapped under separate line item These items are individual conduits, junction boxes or conduit support entries as they are found in "Watts Bar Nuclear Plant Unit No. 1, 3M M20C Radiant Energy Shield 47A243-6-0".

Some items from this report were separated into multiple line items in the walkdown report. For the purposes of this analysis, the conduits were better left intact as a single entry. These items are identified as duplicates and the alternate item number is indicated.

The individual items are reconciled with the TVA walkdown report and listed under the appropriate line items from that report.A small number of items could not be reconciled between the two reports. These are listed in the spreadsheet and no shielding is credited for these line items. This is a conservative approach as all unmapped items are considered to be destroyed.

Once the two input reports were reconciled, the items were mapped in the 3-D CAD model of the plant and each break was analyzed to determine shielding effects on the debris targets. Table 5-2 shows the results of this analysis.

Per the SER, only 25% of the shielding effect is credited.

An electronic copy (on CD) of the CAD model is included with this calculation as part of this Appendix.

ALION-CAL-TVA-2739-03 Revision 3 Appendix 5 5-2 of 5-7 I Table 5-1 -TVA Walkdown Report 11-47A243-6-0 Reconciliation Ildentified Mapped and analyzed for shieldinq Identified Duplicate tarqet, mappd under separate line item INSU oun F)ISLTPE THICKNS Description DESCRPTIO VOLUME (Ii3 Lin. Ft. _ IN I PM026EItem88A 3.020, 03 3R-Z!8/;,722 to 16F'N of E-WV line, Radius- 17'1PM826E .02 .033 90FLIP EL 702 VC441232 0.rn88 34 o.03315 10U From JB4557B R-Z73/732 TO R-Z64/734 R-Z68/754 From JB-6346-B to SPT I1VC4062B Itm8A 0.22 0.0438 5#D1312070109-10-F23981A 1PM822D ,32 .043 30R-Z138/722 Radius 39' to R-Z80/722 Radius 20 1PM822l) Itm 89 1 132 .043 30FLR EL 702 1 VC4041 Itm 9 0.66 0.04386 15 1- 1o~ #D27 3-44A056 s10 1VC4431EBt, ý) 3.39 (1.0522 65R-Z144/74' TO JB-4557-B at R-Z73732 JB-293-455,7-B' 0.rj )A 26 R-Z73/732 Mounted on Crane Wall .JB-293-6347-A02 R-Z125/725 Mounted on Cr-ane Wall 1 PM8026em2 90 6D Supports VC4432B Itm9C10 16D Supports Total 1 inch 1 1.66 13 0.1280 115 WillC Iem692 5 61) Supports 1. 1 PM8022D Itm9E30 61) Supports 1 VC40 itm92 15 6D Supports Total 1.5 inch 0.77 6 0,ý1280 50 2" 1VC4431 B I tm9G165 6D Supports Total 2 inchl 1'.02 8 10. 1280 65 ALION-CAL-TVA-2739-03 Revision 3 Appendix 5 5-3 of 5-7 ILin item INSUL. Insul Vol per II NSULATION I PACKET DiE N ber IN Cu Lin. Ft. OCATION ELEV. OD (IN) LENGTH (FT) INSUL. TYPE THICKNESS DECITO Number I VOLUME (FT3) Con Lin 1t 1OATO ,, 1LETTER1.Description I 1 PM8021D Item 132A 0.66 0.0438 15 3M-M20C 39, FLR EL 702 1PM8022D Item 132B 30.00 3M-M20C Documented as Item 89B R-Z125/725 Radius 40, FROM 1-JB-293-6347-1VC4057A e 13 0 0 2 1 A to R-Z150 FLR EL 702 I 1PM8020DI Item 133A 1 1.30 1 I 0.0522 1 1 I I I 25 3M-M20C['

ALION-CAL-TVA-2739-03 Revision 3 Appendix 5 5-4 of 5-7 DESCRIPTIONOO Line Item INSUL. CunT Ins Vol per AREA I LOCATION I ELEV. tpOD (IN) LENGTH (FT) INSUL. TYPE I TI LATNES I PACKET Description I I I I -I-I I, -I I I I I I I I I I I!I I I I I I I I ALION-CAL-TVA-2739-03 Revision 3 Appendix 5 5-5 of 5-7 Table 5-2 -3M Insulation Shielding Calculations Shieding credited (-25% per SER)Fully Shielded Partially outside ZOI DESCRIPTION Line Kam INSUL LENGTH (FT) Description Break I Vol Break 2 Vol Break 3 Vol Break 4 Vol Number V )I PM8026E Item 88A 3.02 90 R-Z18/722 to 16' N of E-W line, Radius 17', FLR 82' inside ZOI -inside ZOI Outside ZOI Outside ZOI EL 702 10' Shielded b RCP 1 Item 88B 0.50 15 Unknown 1" Conduit, 15' in length 0' Shielded 0.50 O' Shielded 0.50 0 Shielded 0.50 0' Shielded 0.50 1 5'would be inside ZOI 1VC4432B Item 88C 0.34 10 From JB4557B R-Z731732 TO R-Z64/734 but entire length shielded Outside ZOI Outside ZOI Outside ZOI I by RCP1 1VG462B tem 9A 022 5R-Z68(754 From JB-6346-B to SPT 1VC4062# Item 89A 0.22 5 0' Shielded 0.22 Outside ZOI Outside ZOI Outside ZOI_______ ~~~~#01 20701 09-10-F23981A__________

1PM80220 Item 89B 1.32 30 R-Z1 38/722 Radius 35' to R-Z80/722 Radius 20 3.5' Inside ZOI 0.1 3.5'Outside ZOI 16 Outside ZOI Outside ZOI FLR EL 702 1VC464BIte 89C 0.6 is R-Z68/754 From JB-6346-B to SPT 1VC4064 Item 89C 0.66 15 7 -4 6- Outside ZOI Outside ZOI Outside ZOI Outside ZOI_______#D112070111-4-47A056-210 1VC4431B Item 90A 3.39 65 R-Z144/741 TO JB-4557-B at R-Z73/732 Outside ZOI 14.5' Inside ZOI 0.76 Outside ZOI Outside ZOI JB-293-4557-B Item 91A 0.26 R-Z73/732 Mounted on Crane Wall Outside ZOI Outside ZOI Outside ZOI Outside ZOI JB-293-6347-A Item 91B 0.26 R-Z125/725 Mounted on Crane Wall Outside ZOI Shielded b RCP2 Outside ZOI Outside ZOI 1PM8026E 1 inch 90 6D Supports 7 it. inside ZOI Outside ZOI Outside ZOI supports 10' Shielded b RCP 1 1 inch 15 6D Supports 1' Inside ZOI 0'Shielded 0' Shielded 0' Shielded supports 1 nh1.5' would be inside ZOI;V VC4432B 1 inch 10 6D Supports but entire length shielded .Outside ZOI Outside ZOI Outside ZOI supportsby RCP1 82' inside ZOI -22' Inside ZO1 inch support 1.66 1 D Supports 10' Shielded by RCP I 93' Outside ZOI 0.384 15' Inside ZOI 0.256 15' Inside ZOI 0.256 1VC4062B 1.5 inch 5 6D Supports 0'Shielded Outside ZOI Outside ZOI Outside ZOI supports 1PM80221.

inch 30 60 Supports 3.5 Inside ZOI 3.5' Outside ZO Outside ZOI Outside ZO0 supports 1VC4064e 1.5 0nc 15 6D Supports Outside ZOI Outside ZOI Outside ZOI Outside ZOI 1.5, inh,5 6D0Support 0*ShildedCI2 0'Sielded

0.3 Outid

.ZO, Ousd .ZO, split °.5' ,nside zo, 23.5' ouide zoi 1VC4431e s2u 08o2 65 6D Supports Outside ZOI 145' Inside ZOI Outside ZOI Outside ZOI 2 Inch supports 1.02 85 60 Supports Outside ZOI 0 14.5' Inside ZOI 2Moutside ZOI Outside ZOI IPM8021D Item 132A 0.66 15.00 R-I872Rdu 9 oRZ3[2 ais Outside ZOI 0' Shielded 0.66 Outside ZOI Outside ZOI 39, FLR EL 702 1VC4057Ae Item 132C 0.88 20.00 R-Z125/725 Radius 40, FROM 1-JB-293-6347-Outside ZOI 0' Shielded 0,88 Outside ZOI Outside ZOI A to R-Z150 FLR EL 702 1PM8020D Item 133A 1.30 25.00 R-Z150/728 (HVAC opening to Fan Room 2) to Outside ZOI 0' Shielded 1.30 Outside ZOI Outside ZOI R-Z138/722, Radius 39', Floor El 702 Unknown 2" Conduit, 25' in length.It appears that 1/2 of item 363 is included because it is inside the penetration.

If this is the Item 133C 0.65 25.00 case, this item should be included since item 0' Shielded 0.65 0' Shielded 0.65 0' Shielded 0.65 0' Shielded 0.65 133A wraps conduit to the opening in Fan Room 2. It is included herm for the sake of conservativism.

-~1 -

ALION-CAL-TVA-2739-03 Revision 3 Appendix 5 5-6 of 5-7 DESCRIPTION Line Item INSUL. LENGTH (FT) Description Break I Vol Break 2 Vol Break 3 Vol Break 4 Vol Number VOLUME "FT3-1PM8021D 1.5 inch 15.00 7B Supports Outside ZOI 0' Shielded Outside ZOI Outside ZOI supports 1VC4057A 1.5 inch 20.00 7B Supports Outside ZOI 0' Shielded Outside ZOI Outside ZOI supports 1.5 inch 0.64 35 7B Supports Outside ZOI 0 O' Shielded 0.64 Outside ZOI Outside ZOI su"rrP I --1PM80200 2 inch 25.00 7B Supports Outside ZOI 0' Shielded Outside ZOI Outside ZOI supports 2inch 12.50 7B Supports 0 Shielded 0 Shielded 0 Shielded 0' Shielded supports 0' Shielded 2 inch supports 0.64 37.5 7B Supports 25' OutsIde ZOI 0.26 0' Shielded 0.64 12.5' Inside ZOI 0.26 12.5' Inside ZOI 0.26 1VC4063B Item 262A 022 5.00 R-Z681754 From JB-6346-B to Ceiling Outside 70I Outside Z01 Outside 701 Outside Z01 Penetration R-Z66/754

_ _____ ___ Outside Ou eud JB-293-6346-B Item 263A 026 Inside Crane Wall at R-Z681754 Outside ZOI Outside ZOI Outside ZOI Outside ZOI 1VC4063B pportsi 0.26 5.00 10E Supports Outside ZOI Outside ZOI Outside 0II Outside 0OI ITotals 18.93 T Break I (ft 3) Break 2 (fte) Break 3 (ft 3) 1.67 Break 4 (ft 3) 1.?

ALION-CAL-TVA-2739-03 Revision 3 Appendix 5 5-7 of 5-7 AM Invtulatinn -a 3Dmndai Watts Bar Reactor Building GSI-191 Debris Generation Calculation.ALIO 0 N Document No: ALION-CAL-TVA-2739-03 Rev:3 Page: A-1 of A-25 ATTACHMENT A -ENERCON INSULATION SPREADSHEET This Attachment contains the Enercon-provided Watts Bar insulation spreadsheet showing the type, quantity and location of insulation within containment.

This spreadsheet was included with the walkdown report [9] and used to create Appendices 1 through 3.

ALIO N-CAL-TVA-2739-03 Revision 3 Attachment A 2 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS INSUL.PROBLEM OD LENGTH INSUL. INSULATION VOLU JACKET BUCKLE STRAP PACKET NUBR LOCATION ELEV. AREA DESCRIPTION (N (F) TP THCES(I)VOLUME MAEIL TP YECOMMENTS LTE NUMBER (IN) (FT) TYPE THICKNESS (IN)E LETTER SEALANT AROUND SEALANT BET SHEET N/A RACEWAY 702' 1 STAINLESS N/A SEE CALC SC SEE CALC 0.327 N/A N/A N/A METAL AND STEEL A TV CONTAINMENT WALL CONTAINMENT N/A RACEWAY 702' 1 BEHIND PANEL N/A SEE CALC FOAMGLA SEE CALC 260.73 N/A N/A N/A N/A A I SS N/A RACEWAY 702 1 SEALANT AROUND SEALANT APPLIED ALL COVERSWY 02 1N/A N/A N/A N/A N/A N/A N/A N/A ARUD OE COVERS AROUND COVER N/A RACEWAY 702' 1 MIRROR REFLECTIVE SEE CALC WB1- N/A N/A N/A N/A MRI (LETDOWN LINES) C INSULATION N/A N/A N/A DWD-001G NNN/ M(D LE NIA RACEWAY 702' 1 LABELS, SIGNS, & N/A N/A N/A N/A 0.00 N/A N/A N/A SEE REPORT FOR D PENETRATION NO. COMMENTS N/A RACEWAY 702' 1 TIE WRAPS N/A N/A N/A N/A N/A N/A N/A N/A SEE REPORT COMMENTS E N/A RACEWAY 702' 1 CALCIUM SILICATE SEE SEE CALC CALCIUM SEE CALC 56.70 N/A NIA N/A SEE CALCULATION E CALC SILICATE SEAL AROUND N/A RACEWAY 702' 1 PETRON N/A N/A RTV SEE CALC 0.02 N/A NIA N/A N/A F PENETRATION PIPE N/A RACEWAY 702' 1 FOAM IN PENETRATION N/A N/A FOAM SEE CALC 3.18 N/A N/A N/A N/A F 0600200 RACEWAY 702' 1 LETDOWN LINE 3.50 64.75 RMI 1.75 12.98 S.S. STD N/A T OD INSULATION G 09 1 0600200 RACEWAY 702' 1 LETDOWN LINE 2.38 130.34 RMI 1.81 21.57 S&S. STD N/A 6" OD INSULATION G 09 0600200 RACEWAY 702' 1 LETDOWN LINE 2.28 5.34 RMI 4.31 3.31 S.S. STD N/A 11" OD INSULATION G 09 0600200 RACEWAY 702' 1 LETDOWN LINE 2.38 4.36 RMI 0.81 0.25 S&S. STD N/A 4" OD INSULATION G 09 0600200 5" OD INSULATION (2.38" G 09 RACEWAY 702' 1 LETDOWN LINE 2.38 2.70 RMI 1.31 0.28 S.S. STD N/A OD IPING) G 09 ___ ____OD PIPING) ____0600200 5" OD INSULATION (1.06" G 09 RACEWAY 702' 1 LETDOWN LINE 1.06 0.80 RMI 1.97 0.10 S.S. STD N/A 0D PIPING)SEE CALCIUM N/A RACEWAY 702' 1 CALCIUM SILICATE SEE CALC SEE CALC 56.79 N/A N/A N/A SEE CALCULATION G CALC SILICATE N/A RACEWAY 702' 1 EXCESS LETDOWN 1.32 7.46 RMI 2.34 1.39 S.S. STD N/A 6" OD INSULATION i N/A RACEWAY 702' 1 EXCESS LETDOWN 1.32 3.44 RMI 1.84 0.44 S.S. STD N/A 5OD INSULATION i N/A RACEWAY 702' 1 EXCESS LETDOWN 1.32 1.00 RMI 3.84 0.43 S&S. STD N/A 9" OD INSULATION J 0600200 RACEWAYSEAL WATER RETURN 4.50 160.00 RMI 1.75 38.18 S'S. STD N/A 8" OD INSULATION K 06, -07, -13 LINE RACEWAYSEAL WATER RETURN 4.50 2.05 MIN-K 0.75 0.18 N/A N/A N/A 6" OD MIN-K INSULATION K 0602-078-13 LINE _1 06,020-07,-1 SEAL WATER RETURN__ _____ _____________

0600200 RACEWAYSEAL WATER RETURN 4.50 3.79 RMI 1.25 0.59 S.S. STD N/A 7 OD INSULATION K 06, -07, -13 LINE 0600200 SEAL WATER RETURN 5.5" OD MIN-K K RACEWAY 702' 1 4.50 1.58 MIN-K 0.5 0.09 N/A N/A N/A K 06, -07, -13 LINE INSULATION 0600200 SEAL WATER RETURN 6.12" OD MIN-KK RACEWAY 702' 1 4.50 1.52 MIN-K 0.5 0.08 N/A N/A N/AK 06, -07, -13 _____ __ __ LINE _____________________

______________

INSULATION

____0600200 RACEWAYSEAL WATER RETURN 4.50 0.94 RMI 1.625 0.20 S&S. STD N/A 7.75" OD INSULATION K 06, -07, -13 LINE _ I I I ALI ON-CAL-TVA-2739-03 Revision 3 Attachment A 3 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM OD LENGTH INSUL. INSULATION INSUL. JACKET BUCKLE STRAP PACKET NUMBER LOCATION ELEV. AREA DESCRIPTION (IN) (FT) TYPE THICKNESS (IN) VOLUME MATERIAL TYPE TYPE COMMENTSLETTER (FT3) MAEAL TP TYELTR 0600200 RACEWAY 702' 1 SEAL WATER RETURN 3.50 17.54 RMI 1.75 3.52 S.S. STD N/A 7" OD INSULATION K 06.-07,-13 LINE _____________

0600200 SAWAERTUN4.6200O MIN-K(06,2 RACEWAY 702' 1 SEAL WATER RETURN 3.50 1.00 MIN-K 0.56 0.05 N/A N/A N/A INSULATION K 06,0-07.8-13 S LINE R INSULATION 0600200 RACEWAY 702' 1 SEAL WATER RETURN 3.50 2.74 RMI 1.25 0.35 S.S. STD N/A 6" OD INSULATION K 06,2-07-13 SEA LINE RETURN 0600200 RACEWAYSEAL WATER RETURN 1.06 6.87 RMI 1.47 0.56 S.S. STD N/A 4" OD INSULATION K 06. -07. -13 LINE 06002078-RACEWAY 702' 1 L RETURN 1.06 1.37 MIN-K 1.47 0.11 S.S. STD N/A 4" OD MIN-K INSULATION K 06.2-07.-13 R A 2LINE RETURN 0600200 RACEWAYSEAL WATER RETURN 1.06 0.92 RMI 3.97 0.40 S.S. STD N/A 9OD INSULATION K 06, -07, -13 LINE 0600200 RACEWAY 702' 1 L RETURN 2.38 2.76 RMI 1.31 0.29 S.S. STD N/A 5" OD INSULATION K 06,0-07.8-13 R A 2LINE RETURN 0600200 RACEWAY 702' 1 L RETURN 2.38 0.65 RMI 1.81 0.11 S.S. STD N/A 6" OD INSULATION K 06,2-07-13 SEALIWATERETURN 0600200 RACEWAY 702' 1 SEAL WATER RETURN 2.38 2.34 RMI 2.31 0.55 S.S. STD N/A 7" OD INSULATION K 06, -07, -13 LINE 0600200 STEAM GENERATOR 020 RACEWAY 702' 1 GENERATO 4.50 149.59 RMI 2.25 49.57 S.S. STD N/A 9" OD INSULATION L 0F600200 STEAM GENERATOR 02 RACEWAY 702' 1 LOWDOWN 4.50 2.57 RMI 1.75 0.61 S.S. STD N/A OD INSULATION L 02 BLOWDOWN 0600200-07-RACEWAY 702' 1 GENERATOR

.0 1.52 MIN-K 1.375 0.27 S.S. STD N/A 7.25" OD INSULATION L 02 BLOWDOWN 0600200 0.STEAM GENERATOR 020 RACEWAY 702' 1 GENERATO 2.38 1.54 RMI 2.31 0.36 S.S. STD N/A 7" OD INSULATION L 02 RACEWAY 702' 1 BLOWDOWN 4.50 178.00 ___ 28_N 9 SA 0600200 STEAM GENERATOR RACEWAY 702' 1 2.38 1.72 RMI 2.81 0.55 S.S. STD N/A 8" OD INSULATION L 02 ______BLOWOOWN________

0600200 RACEWAY 702' 1 STEAM GENERATOR 4.50 178.00 RMI 2.25 58.98 S.S. STD N/A 9" OD INSULATION M 03 1 BLOWDOWN 0600200 STEAM GENERATOR RACEWAY 702' 1LOWDOWN 2.38 1.278 RMI 2.5 0.35 S.S. STD N/A 8 _OD INSULATION M 03 BLOWDOWN___

0600200 STEAM GENERATOR RACEWAY 702' 1 LOWOWN .2. RMI 3.5 0.8 S.S. STD N/A 9" OD INSULATION IM 03 BLOWDOWN___

0600200-07-RACEWAY 702' 1 GENERATOR 2.38 1.48 RMI 2.31 0.35 S.S. STD N/A 7" OD INSULATION M 03 BLOWDOWN N/A00200-07-2STEARCINTERIMLG SESETORRI E AC 886 .. ST I /0600200 702' ENERATO 2.38 2.00 RMI 3.31 0.82 S.S. STD N/A 9" OD INSULATION M 0 R 7BLOWOWN 0600200 STEAM GENERATOR 13" 00 INSULATION RACEWAY 702' 1 8.62 0.73 RMI 2.19 0.38 S.S. STD N/A M 03 B_____ __ LOWDOWN ____ ___ FLANGE)N/A LOOP 1 702' 2 RC INTERIM LEG SEE CALC RMI SEE CALC 88.62 S.S. STO N/A N/A A REACTOR COOLANT SEE N/A LOOP 1 702' 2 PMCACSEE CALC RMI SEE CALC 63.45 S.S. STO N/A N/A 8 0600200 LOOP 1 702' 2 INTERIM LEG DRAIN 2.38 0.88 RMI 3.8125 0.45 S.S. STO N/A 10" 00 INSULATION C 09O9 __________________________

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ALION-CAL-TVA-2739-03 Revision 3 Attachment A 4 of 25 WAITS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM LOCATION ELEV. AREA OD LENGTH INSUL. INSULATION INSUL. C S PACKET NUMBER DESCRIPTION (IN) (FT) TYPE THICKNESS (IN) VOLUME MATERIAL TYPE TYPE LETTER 002 (FT3)0600200 LOOP 1 702' 2 INTERIM LEG DRAIN 2.38 14.00 RMI 2.8125 4.46 S.S. STD N/A 8" OD INSULATION C 09 0600200 LOOP 1 702' 2 INTERIM LEG DRAIN 2.38 0.55 RMI 2.3125 0.13 S.S. STD N/A T' OD INSULATION C 09 _ _ 1 0600200-1 LOOP 1 702' 2 INTERIM LEG DRAIN 2.38 0.50 RMI 1.3125 0.05 S.S. STD N/A 5" OD INSULATION C 09 NIA LOOP1 702' 2 LABELS, SIGNS, & N/A N/A NIA N/A 0.00 N/A N/A N/A SEE REPORT FOR D PENETRATION NO. COMMENTS N/A LOOP 2 702' 3 RC INTERIM LEG SEE CALC RMI SEE CALC 86.81 S.S. STD N/A N/A A CALC REACTOR COOLANT SEE N/A LOOP 2 702' 3 PUMP CALC SEE CALC RMI SEE CALC 63.45 S.S. STD N/A N/A B PUMP CALC 0600200 0 0 LOOP 2 702' 3 INTERIM LEG DRAIN 2.38 0.88 RMI 3.8125 0.45 S.S. STD N/A 10" OD INSULATION C 0600200-1 LOOP 2 702' 3 INTERIM LEG DRAIN 2.38 14.00 RMI 2.8125 4.46 S.S. STD N/A 8" OD INSULATION C 10 1 N/A LOOP2 702' 3 CALCIUM SILICATE SEE SEE CALC CALCIUM SEE CALC 70.68 N/A N/A N/A SEE CALCULATION D CALC SILICATE SEE N/A LOOP 3 702' 4 RC INTERIM LEG SEE CALC RMI SEE CALC 85.43 S.S. STD N/A N/A A CALC N/A LOOP 3 702' 4 INTERIM LEG DRAIN 2.38 1.92 RMI 3.8125 0.99 S.S. STD N/A 10" OD INSULATION B N/A LOOP 3 702' 4 INTERIM LEG DRAIN 2.38 9.50 RMI 2.8125 3.02 S.S. STD N/A 8" OD INSULATION 8 0600200 0 0 LOOP 3 702' 4 LETDOWN LINE 3.50 13.25 RMI 3.25 6.34 S.S. STD N/A 10" OD INSULATION C 10REACTOR COOLANT SEE N/A LOOP 3 702' 4 RECO COLN SEE CALC RMI SEE CALC 63.45 S.S. STD N/A N/A D PUMP CALC_______________

SEE CALCIUM N/A LOOP 3 702' 4 CALCIUM SILICATE SEE CALC SEE CALC 42.24 N/A N/A N/A SEE CALCULATION E CALC SILICATE N/A LOOP 4 702' 5 RC INTERIM LEG SEE CALC RMI SEE CALC 85.05 S.S. STD N/A N/A A CALC N/A LOOP4 702' 5 REACTORSEE CALC RMI SEE CALC 63.45 S.S. STD N/A N/A B PUMP CALC 0600200 LOOP 4 702' 5 INTERIM LEG DRAIN 2.38 1.92 RMI 3.8125 0.99 S.S. STO N/A 10" OD INSULATION C 12 0600200 LOOP 4 702' 5 INTERIM LEG DRAIN 2.38 12.92 RMI 2.8125 4.11 S.S. STD N/A 8" OD INSULATION C 12 N/A LOP 4 02' 5 MIN K TO WASTE DISP N/A LOOP_ 4 702' 5 LINE -4.50 2.00 MIN-K SEE CALC 0.05 N/A N/A N/A WRAP AROUND 4" PIPE D LINEII N/A LOOP 4 702' 5 TAGS, LABELS, & SIGNS N/A N/A N/A N/A N/A N/A N/A N/A SEE REPORT FOR E I _COMMENTS 0600200 RESIDUAL HEAT 14.00 58.75 RMI 2 41.02 S.S. STD N/A 18" OD INSULATION F 01 LO4 70' 5REMOVAL 1____0600200 LOOP 4 702' 5 RESIDUAL HEAT 14.00 5.00 RMI 1 1.64 S.S. STO N/A 16" OD INSULATION F 01 REMOVAL I 01 LOOP 4 702' 5 RESIDUAL HEAT 14.00 1.83 RMI 1.75 1.10 .S. STD , N/A 17.5" OD INSULATION F 060020-03 REMOVAL I____ I____ __________

I_____ I____

ALION-CAL-TVA-2739-03 Revision 3 Attachment A 5 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM LOCATION ELEV. AREA DESCRIPTION OD LENGTH INSUL. INSULATION INSUL. JACKET BUCKLE STRAP PACKET NUMBER (IN) (FT) TYPE THICKNESS (IN) (FT3) MATERIAL TYPE TYPE LETTER 0602003- RESIDUAHEAT(FT3) 0600200 4 702' 5 RESIDUAL HEAT 10.75 15.67 RMI 2.125 9.35 S.S. STD N/A 15" OD INSULATION F 01 REMOVAL 0600200 LOOP4 702' 5 14.00 3.13 RMI 12 21.31 S.S. STD N/A 3800 INSULATIONF 01 REMOVAL .(VALVE)002003- LO4 70 5 REMOVUAL HET33" 0D INSULATION 0600200 LOOP4 702' 5 10.75 2.75 RMI 11.125 14.60 S.S. STD N/A (VLVE)ISULATIONF 01 REMOVAL I(VALVE)0600200 RESIDUAL HEAT LOOP 4 702' 5 1.05 1.13 RMI 1.475 0.09 S.S. STD N/A 4 OD INSULATION F 01 REMOVAL 0600200 LOOPRESIDUAL HEAT 1.05 2.21 RMI 2.475 0.42 S.S. STD N/A 6OD INSULATION F 01 REMOVAL 0600200 LOOPRESIDUAL HEAT 6.63 2.91 RMI 0.6875 0.32 S.S. STD N/A 8" OD INSULATION F 01 REMOVAL 0600200 LOOPRESIDUAL HEAT 6.63 2.05 RMI 8.6875 5.95 S.S. STD N/A 24" OD INSULATION F 01 REMOVAL N/A LOOP 1 716' 6 STEAM GENERATOR SE SEE CAL RMI SEE CALC 215.60 S.S. ST N/A N/A A CALC E AE L6SA N/A LOOP 1 716' 6 STEAM GENERATOR SEE SEE CALC RMI SEE CALC 0.66 S.S. STD N/A AT ROOT VALVES A CALC 0600200 LOOP 1 716' 6 FEEDWATER 16.00 24.10 RMI 2.5 24.32 S.S. STD N/A 21" OD INSULATION B 01 0600200 LOOP 1 716' 6 FEEDWATER 16.00 10.59 RMI 0.5 1.91 S.S. STD N/A 17" OD INSULATION B 01 0600200 LOOP 1 716' 6 FEEDWATER SEE SEE CALC RMI SEE CALC 0.42 S.S. STD N/A AT 1.88" OD LINE B 01 CALC 0600200 SEE LOOP 1 716' 6 FEEDWATER SEE CALC RMI SEE CALC 0.26 S.S. STD N/A AT 1" LINE B 01 CALC 0600200 LOOP1 716' 6 FEEDWATER 30.25 0.5 2 0.70 N/A STD N/A AT PENETRATION

X-12A 8 01 WOOL SEE PAINT INSPECTION N/A LOOP 1 716' 6 PAINT CHIP N/A N/A N/A N/A 0.00 N/A N/A N/A EPORTC REPORT N/A LOOP 1 716' 6 CONDUIT 3M-M2OC 1.32 N/A 3M-M20C 0.1875 2.35 N/A N/A N/A SEE CALCULATION D INSULATION I N/A LOOP 1 716' 6 CONDUIT 3M-M2OC 1.90 N/A 3M-M20C 0.1875 1.43 N/A N/A N/A SEE CALCULATION D INSULATION I N/A LOOP 1 716' 6 CONDUIT3M-M2OC 2.38 N/A 3M-M20C 0.1875 1.70 N/A N/A N/A SEE CALCULATION D INSULATION I CONDUIT 3M-M2OC JUNCTION BOXES SEE N/A LOOP1 716' 6 N/A N/A N/A N/A 0.52 N/A N/A N/A CALCLATOND INSULATION I CALCULATION N/A LOOP1 716' 6 N/A N/A N/A N/A 2.31 N/A N/A N/A SUPPORTDSEE INSULATION CALCULATION LABELS, TAGS, AND TIE SEE REPORT FOR N/A LOOP 1 710-720 6 WRAPS N/A N/A N/A N/A N/A N/A N/A N/A COM T FE WRAPS COMMENTS 0600200 LOOP4" PRESSURIZER SPRAY 4.50 43.40 RMI 2.75 18.88 S.S. STD N/A 10" OD INSULATION F 02 LfNE I-0600200 LOOP 1 716' 6 4" PRESSURIZER SPRAY 4.50 1.21 RMI 0.75 0.10 S.S. STD N/A 6" OD INSULATION F 02 1 LINE I I I I I ALION-CAL-TVA-2739-03 Revision 3 Attachment A 6 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS INSUL.,ACE PROBLEM OD LENGTH INSUL. INSULATION VOLU JACKET BUCKLE STRAP PACKET NUBR LOCATION ELEV. AREA DESCRIPTION (N (F) TP THCES(I)VOLUME MAEIL TP YECOMMENTS LTE NUMBER (IN) (FT) TYPE THICKNESS (IN)0600200-13 4"____PRESSUR____ (F3ZMATRILSYPE TYEY 0600200 LOOP4" PRESSURIZER SPRAY 4.50 0.67 MIN-K 1.5 0.13 S.S. STD N/A 7.5" OD INSULATION F 02 LINE 0600200 LOOP4" PRESSURIZER SPRAY 4.50 1.21 RMI 7.75 2.51 S.S. STD N/A 20" OD INSULATION F 02 LINE 0600200 LOOP1 716' 6 L/4" PRESSURIZER SPRAY 00204 YPR SSR S 1.05 5.17 RMI 2.975 1.35 S.S. STD N/A 7" OD INSULATION F 02 LO1 71' 6 BYPASS LINE ____0600200 3/4" PRESSURIZER SPRAY 020 LOOP1 716' 6 PR SSURIZE 1.05 4.34 RMI 1.475 0.35 S.S. STD N/A 4OD INSULATION F 02 LO1 71' 6 BYPASS LINE 0600200 LOOP3/4" PRESSURIZER SPRAY 1.05 0.50 RMI 3.35 0.16 S.S. STD N/A 7.5" OD INSULATION F 02 BYPASS LINE I N/A LOOP 1 716' 6 HOT LEG SEE CALC RMI SEE CALC 69.55 S.S. STD N/A N/A G CALCI N/A LOOP1 716' 6 COLD LEG SEE CALC RMI SEE CALC 55.34 S.S. STD N/A N/A H N/A OOP1 71' 6COLDLEG CALC 0600200 06 LOOP 1 716' 6 BORON INJECTION 1.90 5.65 RMI 2.55 1.40 S.S. STD N/A T7OD INSULATION J 05 00200- LOOP 1 716' 6 BORON INJECTION 1.90 0.96 RMI 7.6 1.51 S.S. STO N/A 9.500O INSULATION J 0600200 LOOP 1 716' 6 ACCUMULATOR 10.75 2.36 RMI 0.795 0.47 S.S. STD N/A 12.34" OD INSULATION K 01 _________

INJECTION

__________

____ ____ ___0600200 ACCUMULATOR 060 LOOP1 716' 6 ACC TOR 10.75 16.42 RMI 3.125 15.53 S.S. STD N/A 17" OD INSULATION K 01 INJECTION 0600200 ACCUMULATOR 060 LOOP1 716' 6 ACC TOR 10.75 2.65 MIN-K 1.25 0.87 S.S. STD N/A 13.250" OD INSULATION K 01 LO1 71' 6INJECTION

__________

___0600200 ACCUMULATOR 06 LOOP 1 716' 6 ACC TOR 10.75 5.09 RMI 9.635 21.81 S.S. STD N/A 30" OD INSULATION K 01 ______INJECTION

______ ____ ____0600200 ACCUMUL 6 LOHE AFTOR 0600 IN00A C TO 10.75 0.57 RMI 6.126 1.29 S.S. STD N/A 23" OD INSULATION K 01 LO1 71' 6INJECTION_________

0600200 LOWHEASIDU SAT 6.63 7.94 RMI 2.6875 4.90 S.S. STD N/A 12"O0 INSULATION S N/A LOOP 1 716' 6 RESIDUAL HEAT 6.63 3.59 RMI 3.6875 2.93 S.S. STD N/A 14" OD INSULATION M REMOVAL HEAT N/A LOOP 1 716' 6 RESIDUAL HEAT 6.63 2.10 RMI 0.6875 0.23 S.S. STD N/A 86" OD INSULATION M REMOVAL RESIDUAL HEAT N/A LOOP 1 716' 6 REMOVAL 6.63 2.10 RMI 9.6875 0.48 S.S. STD N/A 26" OD INSULATION M REMOVAL N/A LOOP 1 716' 6 RESIDUAL HEAT 8.63 1.10 MIN-K 0.9375 0.22 S.S. STD N/A 10.5" OD INSULATION M REMOVAL 11A LOOP 1 716' 6 NORMAL CHARGING 3.50 54.50 RMI 2.75 20.44 S.S. STD N/A 9" 00 INSULATION N 0600200 LOOP 1 716' 6 NORMAL CHARGING 3.50 0.89 RMI 1.5 0.15 S.S. STD N/A 6.5" OD INSULATION N 11 1 REMO 0600200 LOOP 1 716' 6 NORMAL CHARGING 3.50 2.50 RMI 2 0.60 S.S. STO N/A 7.5" 00 INSULATION N 11 _ _III ALION-CAL-TVA-2739-03 Revision 3 Attachment A 7 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM OD LENGTH INSUL. INSULATION INSUL. JACKET BUCKLE STRAP PACKET NUMBER LOCATION ELEV. AREA DESCRIPTION (IN) (FT) TYPE THICKNESS (IN) (FL3M MATERIAL TYPE TYPE LETTER NUMBERM(FT3)LET 00200- LOOP 1 716' 6 STEAM GENERATOR 3.60 41.67 RMI 2.25 11.76 S.S. ST D N/A 8 " 00 INSULATION P 0600200-07-STAGERTO 01 B_____ LOWDOWN____

01 LOOP6 -716' 6 BLOWDOWN 4.50 28.75 RMI 2.25 9.63 S.S. STD N/A 9 " OD INSULATION P 0600200 STEAM GENERATOR 01 LO O P 1 716' 6 LO W DO W N4.50 3. 5 RM I .5 .S.S STD N/A 6" O D INSU LATIO N P 0600200 STEAM GENERATOR 4.50 3.01 RMI 0.75 0.26 S.S. STD N/A 6 00 INSULATION P 01 BLOWDOWN LOOP 1 716' 6 1.35 0.59 RMI 3.325 0.20 S.S. STD N/A 8 OD INSULATION P 01 BLOWDOWN 0600200 LOOPSTEAM GENERATOR 1.33 1.22 RMI 3.335 0.41 S.S. STD N/A 8" OD INSULATION P 01 BLOWDOWN 0600200 LOOPSTEAM GENERATOR 1.31 0.75 RMI 2.345 0.14 S.S, STD N/A 6 OD INSULATION P 01 BLOWDOWN 0600200 LOOPSTEAM GENERATOR 1.30 1.13 RMI 3.35 0.38 S.S. STD N/A 8" OD INSULATION P 01 BLOWDOWN 06020007-STEM1G NER TOR 2.91 0.29 RMI 2.04 5 0.06 S.S , ST D N/A 7' 00 INSULATION P 0600200 STEAM GENERATOR N/A LOOP 1 716' 6 MIN-K N/A N/A MIN-K 3.38 0.944 N/A N/A N/A N/A Q 0 0 LOOP 1 716' 6 3" ALTERNATE CHARGING 3.50 44.09 RMI 2.75 16.53 S.5. STD N/A 9 OD INSULATION R 0 0 LOOP 1 716' 6 3" ALTERNATE CHARGING 3.50 1.83 MIN-K 1.25 0.24 S.S , STD N/A 6" OD INSULATION R SEE N/A LOOP 2 716' 7 STEAM GENERATOR SESEE CALC RMI SEE CALC 215.60 S.S& STD N/A N/A A CALC N/A LOOP 2 716' 7 STEAM GENERATOR SEE SEE CALC RMI SEE CALC 0.67 S.S. STD N/A AT ROOT VALVES A 7_ 6__ CALC N/A LOOP 2 716' 7 C NSU IT 0 1.90 50.00 3M-M20C 0.1875 2.19 N/A N/A N/A SEE CALCULATION B CONDUIT 3M-M20C______ ~~INS ULATION ______________

___ ___N/A LOOP2 716' 7 CNSUION 2.38 70.00 3M-M20C 0.1875 3.65 N/A N/A N/A SEE CALCULATION B CONDUIT 3M-M20C SUPPORT INSULATION N/A LOOP 2 716 7 INSULTI N/A N/A 3M-M2OC N/A 1.79 N/A N/A N/A SEE CALULATION B INSULATION SEE CALCULATION 0600200 LOOPPRESSURIZER SURGE 14.00 34.40 RMI 4.5 62.48 S.S. STD N/A 23" OD INSULATIONS C 01 LOP2 76 'LINE ______________

0600200 PRESSURIZER SURGE 01 LOP2 76L RSUIZER UG 0 LOOP2 716' 7 14.00 7.67 RMI 0.5 1.21 S.S. STD N/A 15"OD INSULATIONS C 0600200 PRESSURIZER SURGE 0600200 LOOP 2 716' 7 PRESSURIZER SURGE 14.00 3.34 RMI 1 1.09 S.S. STD N/A 16" OD INSULATIONS C 01 ___ LINE__________

0600200 LOOP 2 716' 7 PRESSURIZER SURGE 14.00 3.01 RMI 2.5 2.71 S.S. STD N/A 19" OD INSULATIONS C 01 716 LINE __________

0600200 1 PRESSURIZER SURGE 01_LOOP2 716' 7 LINE 14.00 8.67 RMI 1.5 4.40 S.S. STD N/A 17" OD INSULATIONS C 0600200 LOOP 2 716' 7 FEEDWATER 16.00 18.50 RMI 2.5 18.67] 6.6. STID N/A 2100O INSULATION D 0600200 PR S U I E U G 02 LOOP 2 716' 7 FEEDWATER 16.00 0.80 RMI 2 0.63 S.S. STD N/A 20" OD INSULATION D 0600200 9 02 LOOP 2 716' 7 FEEDWATER 16.00 1.59 MIN-K 1 0.59 S.S , STD N/A 18" OD INSULATION D 060200

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ALION -CAL-TVA-2739-03 Revision 3 Attachment A 8 of 25 WATTS BAR NUCLEAR PLANT UNIT I WALK DOWN RESULTS PROBLEM ROD LENGTH INSUL. INSULATION INSUL. JACKET BUCKLE STRAP PACKET NUMBER (IN) (FT) TYPE THICKNESS (IN) (FT3) MATERIAL TYPE TYPE LETTER 0T00200-02-3)

A T 02 LOOP 2 716' 7 FEEDWATER 16.00 10.84 RMI 0.5 1.95 S.S. STD N/A 17" OD INSULATION D 02 0600200 SEE 02 LOOP 2 716' 7 FEEDWATER CALC SEE CALC RMI SEE CALC 0.42 S.S. STD N/A AT 1.88" OD LINE D 0600200 SEE 02 LOOP 2 716' 7 FEEDWATER CALC SEE CALC RMI SEE CALC 0.27 S.S. STD N/A AT 1" LINE D 0600200 MINERAL 02 LOOP 2 716' 7 FEEDWATER 30.25 0.50 MNRL 2 0.70 N/A STD N/A AT PENETRATION

X-12B D 02 _____ __WOOL ___ _______ ___0600200 4" PRESSURIZER SPRAY 02 LOOP 2 716' 7 LINE 4.50 32.67 RMI 7,75 14.21 S.S. STD N/A 10" OD INSULATION E T600200 4" PRESSURIZER SPRAY 02 LOOP 2 716' 7 LINE 4.50 1.21 RMI 7,75 2.51 S.S. STD N/A 20" OD INSULATION E 0600200 3/4" PRESSURINE 02 LOOP 2 716' 7 1.05 0.42 RMI 2.975 0.11 S.S. STD N/A 7" OD INSULATION E 02 BYPASS LINE 0600200 3/4" PRESSURIZER SPRAY 1.05 8.42 RMI 02 LOOP 2 716' 7 BYPASS LINE .9 8,2 MI 1.475 0.68 S.S. STD N/A 4" OD INSULATION E N/A LOOP 2 716' 7 HOT LEG SEE SEE CALC RMI SEE CALC 74.60 S.S. STD N/A N/A F CALC N/A LOOP 2 716' 7 HOT LEG SEE CALC RMI SEE CALC 8.15 S.S. STD N/A AT 6" SAFETY INJECTION F CALC N/A LOOP2 716' 7 COLDLEG SEE CALC RMI SEE CALC 55.42 S.S. STD N/A N/A G N/A____ LOOP_2_716_7_COL

__LECALC 0600200 LOOP 2 716' 7 BORON INJECTION 1.90 3.94 RMI 2.55 0.98 S.S. STD N/A 7OD INSULATION H 06 0600200 06 LOOP 2 716' 7 BORON INJECTION 1.90 1.08 RMI 7,6 1.70 S.S. STD N/A 9.5" OD INSULATION H 0600200 ACCUMULATOR 02 LOOP 2 716' 7 INJECTION 10.75 17.75 RMI 3.125 16.79 S.S. STD N/A 17" OD INSULATION J 0600200 LOOPACCUMULATOR 10.75 4.98 RMI 9.625 21.31 S.S. STD N/A 30" OD INSULATION J 02 INJECTION 0600200 LOP 1' 7 ACCUMULATOR 02 2N71CTI7 10.75 0,96 RMI 0,625 0.15 S.S. STID N/A 12" OD INSULATION J 0600200 LOP 1' 7 ACCUMULATOR 10.75 0.96 RMI 0.625 0.154 S.S. STD N/A 1200O INSULATION 02 INJECTION 0600200 ACT2 716' 7 10.75 1.24 RMI 1.625 0.54 S.S. STD N/A 14" OD INSULATION J 02 INJECTION 02 OLPWHE71SAFETY 6.63 9.75 RMI 2.6875 5.32 S.S. STD N/A 1200O INSULATION K 06020-9 LO2 71' INJECTION

____N/ARESIDUAL HEAT 8.63 31.25 RMI 1.1875 7.94 S.S. STD N/A 11" OD INSULATION L REMOVAL RESIDUL EAT9.75" 00 MIN-K N/ARESIDUAL HEAT 8.63 2.74 MIN-K 0.5625 0.31 S.S. STD N/A L REMOVAL INSULATION 0600200 LOOP 2 716' 7 NORMAL CHARGING 3.50 26.92 RMI 2.75 10.09 S.S. STD N/A 9" OD INSULATION M 11 0600200 LOOP 2 716' 7 NORMAL CHARGING 3.50 1.92 RMI 0.5 0.08 S.S. STD N/A 4.5" OD INSULATION M 600200 LOOP 2 716' 7 NORMAL CHARGING 3.50 0.84 RMI 1 0.08 S.S. STD N/A M 11 1 1 1 1 1 1 INSULATION ALl ON-CAL-TVA-2739-03 Revision 3 Attachment A 9 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM DD LENGTH INSUL. INSULATION JACKET BUCKLE STRAP PACKET VOSL.M COMMENTS NUMBER LOCATION ELEV. AREA DESCRIPTION (IN) (FT) TYPE THICKNESS (IN) (FT3) MATERIAL TYPE TYPE LETTER 0602-8-(FT3) 0600200 LOOP 2 716' 7 NORMAL CHARGING 3.50 3.17 RMI 0.75 0.22 S.S. STD N/A 5 OD INSULATION M 11 0 60 0 2 0 0 -0 8 -L O O 2 LOOP 2 716' 7 EXCESS LETDOWN 1.32 39.67 RMI 2.34 7.41 S.S. STD N/A 6 OD INSULATION N T600200 II 0 2 LOOP 2 716' 7 EXCESS LETDOWN 1.32 3.87 MIN-K 2.34 0.72 S.S. STD N/A 6" OD INSULATION N 0600200-08 LOOP 2 716' 7 EXCESS LETDOWN 1.32 6.75 RMI 1.84 0.86 S.S. STD N/A 5OD INSULATION N 12 0600200 LOOP 2 716' 7 EXCESS LETDOWN 1.32 0.59 RMI 0.84 0.02 S.S. STD N/A 3" OD INSULATION N 12 1 0600200 LOOP2 716' 7 STEAM GENERATOR 3.50 35.25 RMI 2.25 9.95 S.S. STD N/A 8OD INSULATION P 02 BLOWDOWN 0600200 STEAM GENERATOR 4.50 28.59 RMI 2.25 9.47 S.S. STD N/A 9OD INSULATION P 02 LOP076 BLOWOOWN 716_ 7 STEAM GEERTO 0600200 STEAM GENERATOR 4.50 3.50 RMI 1.25 0.55 S.S. STD N/A 7" OD INSULATION P 02 LOP2 76B LOWDOWN __________

0600200 LOOP2 716' 7 STEAM GENERATOR 1.31 1.67 RMI 2.845 0.43 S.S. STD N/A 7"OD INSULATION P 02 BLOWDOWN 0600200 LOOP2 716' 7 STEAM GENERATOR 1.31 0.73 RMI 2.345 0.14 S.S. STD N/A 6" OD INSULATION P 02 BLOWDOWN 0600200 LOOP2 716' 7 STEAM GENERATOR 1.31 0.59 RMI 3.345 0.20 S.S. STD N/A 8" OD INSULATION P 02 BLOWDOWN 0600200 LOOP2 716' 7 STEAM GENERATOR 2.88 0.28 RMI 2.06 0.06 S.S. STD N/A 7" OD INSULATION P 02 BLOWDOWN I N/A LOOP 2 720-737 7 CONDUIT INSULATION 3M 1.32 45.00 3M20C SEE CALC 1.51 N/A N/A N/A SEE CALCULATION a RADIANT N/A LOOP 2 720-737 7 SUPPORT N/A N/A N/A SEE CALC 0.77 N/A N/A N/A SEE CALCULATION a 0600200 0 0 LOOP 2 716' 7 LETDOWN LINE 3.50 2.17 RMI 4.25 1.56 S.S. STD N/A 12" OD INSULATION R 10 _________

___0600200 LOOP 2 716' 7 LETDOWN LINE 3.50 47.50 RMI 3.25 22.73 S.S. STD N/A 10" OD INSULATION R 10111 0600200 LOOP 2 716' 7 LETDOWN LINE 3.50 4.29 RMI 2.25 1.21 S.S. STD N/A 8" OD INSULATION R 10 0600200 0 0 LOOP 2 716' 7 LETDOWN LINE 3.50 3.09 RMI 1.5 0.51 S.S. STD N/A 6.5" OD INSULATION R 10 ____0600200 0 0 LOOP 2 716' 7 LETDOWN LINE 3.50 0.59 MIN-K 0.75 0.04 S.S. STD N/A AT MIN-K INSULATION R 060200 LOOP 2 716' 7 3" ALTERNATE CHARGING 3.50 25.09 RMI 2.75 9.41 S.S. STD N/A 9" OD INSULATION S 1111 0600200 LOOP 2 716' 7 3" ALTERNATE CHARGING 3.50 1.25 RMI 0.5 0.05 S.S. STD N/A 4.5" OD INSULATION S 1111 0600200 LOOP 2 716' 7 3" ALTERNATE CHARGING 3.50 3.04 RMI 0.75 0.21 S.S. STD N/A 5OD INSULATION S-1111 N/A LOOP 3 716' 8 STEAM GENERATOR SEE SEE CALC RMI SEE CALC 215.60 S.S. STD N/A NIA A CALC N/A LOOP3 716' 8 STEAM GENERATOR SEE CALC RMI SEE CALC 0.62 S.S. STD N/A AT ROOT VALVES A N/A____ LOOP__ 3_7__8_TEAMGENEATO CALC I I ALION-CAL-TVA-2739-03 Revision 3 Attachment A 10 of 25 WAITS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS INSUL.PROBLEM LOCATION ELEV. AREA DESCRIPTION OD LENGTH INSUL. INSULATION VOLUME JACKET BUCKLE STRAP PACKET NUMBER (IN) (FT) TYPE THICKNESS (IN) (FL3) MATERIAL TYPE TYPE LETTER 0602 -(FT3)0600200 LOOP 3 716' 8 FEEDWATER 16.00 19.42 RMI 2.5 19.60 S.S.. STD N/A 21" OD INSULATION B 03 0600200 LOOP 3 716' 8 FEEDWATER 16.00 1.09 RMI 2 0.86 S.S. STD N/A 19" OD INSULATION B 03 0600200 LOOP 3 716' 8 FEEDWATER 16.00 6.34 RMI 0.5 1.14 S.S. STD N/A 17" OD INSULATION B 03 0600200 LOOP 3 716' 8 FEEDWATER SEE CALC RMI SEE CALC 0.35 S.S. STD N/A AT 1.88" OD LINE B 03 CALC 1 0600200 SEE LOOP 3 716' 8 FEEDWATER SEE CALC RMI SEE CALC 0.24 S.S. STD N/A AT 1" LINE B 03 CALC I 600200 LOOP3 716' 8 FEEDWATER 30.25 0.50 2 0.70 N/A STD N/A AT PENETRATION

X-12C B 03 WOOL 0600200 LOOP 3 716' 8 LETDOWN LINE 3.50 38.50 RMI 3.25 18.43 S.S. STD N/A 10" OD INSULATION C 10 1 N/A LOOP 3 716' 8 HOT LEG SEE CALC RMI SEE CALC 49.89 S.S. STD N/A N/A D CALC N/A LOOP 3 716' 8 COLD LEG SEE SEE CALC RMI SEE CALC 54.98 S.S. STD N/A N/A E CALC 0600200 06 LOOP 3 716' 8 BORON INJECTION 1.90 5.20 RMI 2.55 1.29 S.S. STD N/A T'OD INSULATION F 0600200 06 LOOP 3 716' 8 BORON INJECTION 1.90 0.96 RMI 7.6 1.51 S.S. STD N/A 9.5" OD INSULATION F 600200 LOOPACCUMULATOR 10.75 17.25 RMI 3.125 16.32 S.S. STD N/A 17" OD INSULATION G 02 INJECTION 0600200 LOOP 3 716' 8 ACCUMULATOR 10.75 5.18 RMI 9.625 22.16 S.S. STD N/A 30" OD INSULATION G 02 INJECTION 0600200 LOOPACCUMULATOR 10.75 1.07 RMI 0.625 0.17 S.S. STD N/A 12" OD INSULATION G 02 INJECTION 0600200 LOOPACCUMULATOR 10.75 1.82 RMI 0.375 0.17 S.S. STD N/A 11.5" OD INSULATION G L2 INJECTION 0600200 LOOPLOWHEAD SAFETY 6.63 2.53 RMI 2.6875 1.38 S.S. STD N/A 12" OD INSULATION H 02 INJECTION 0600200 LOOPLOWHEAD SAFETY 6.63 4.26 RMI 0.6875 0.47 S.S. STD N/A 8" OD INSULATION H 02 INJECTION N/A LOOP 3 716' RESIDUAL HEAT 8.63 6.09 RMI 1.1875 1.55 S.S. STD N/A 11" OD INSULATION J REMOVAL N/A LOOP 3 716' 8 RESIDUAL HEAT 6.63 2.17 RMI 9.6875 7.48 S.S. STD N/A 2600 INSULATION REMOVAL I (VALVE)N/A LOOP 3 716' 8 RESIDUAL HEAT 6.63 3.75 RMI 0.6875 0.41 S.S. STD N/A 8" OD INSULATION J REMOVAL N/A LOOP 3 716' 8 RESIDUAL HEAT 6.63 2.67 RMI 3.6875 2.22 S.S. STD N/A 14" OD INSULATION J REMOVAL 0600200 0 2 LOOP 3 716' 8 EXCESS LETDOWN 1.32 42.84 RMI 2.34 8.00 S.S. STD N/A 6" OD INSULATION K 12 0600200 7' 00 INSULATION LOOP 3 716' 8 EXCESS LETDOWN 1.32 0.63 RMI 2.84 0.16 S.S. STD N/A K 12 (VALVE)

ALION-CAL-TVA-2739-03 Revision 3 Attachment A 11 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS INSUL. PCE PROBLEM LOCATION ELEV. AREA DESCRIPTION OD LENGTH INSUL. INSULATION VOLUME JACKET BUCKLE STRAP COMMENTS PACKET NUMBER (IN) (FT) TYPE THICKNESS (IN) (FT3) MATERIAL TYPE TYPE LETTER______ ____________________(FT3)

MAEIL TYE TP 0600200 LOOP 3 716' 8 EXCESS LETDOWN 1.32 6.17 RMI 1.84 0.78 S.S. STD N/A 5" OD INSULATION K 12 0600200 T 12 LOOP 3 716' 8 EXCESS LETDOWN 1.05 0.78 RMI 1.975 0.10 S.S. STD N/A 5" OD INSULATION K 12 6" OD INSULATION 0600200 LOOP 3 716' 8 EXCESS LETDOWN 1.05 0.46 RMI 2.475 0.09 S.S. STD N/A 6 ALVEINULATIONK 12 (VALVE)0600200 STEAM GENERATOR LOOP 3 716' 8 3.50 44.92 RMI 2.25 12.68 S.S. STD N/A 8" OD INSULATION L 03 BLOWDOWN 0600200 LOOPSTEAM GENERATOR 4.50 21.42 RMI 2.25 7.10 S.S. STD N/A 9OD INSULATION L 03 BLOWDOWN 1 0600200 LOOPSTEAM GENERATOR 4.50 3.17 RMI 1.25 0.50 S.S. STO N/A 7OD INSULATION L 03 BLOWDOWN 0600200 LOP 1' 8 STEAM GENERATOR 1.31 1.75 RMI 2.845 0.45 S.S. STD N/A 7" 00 INSULATION L LOP0316 BLOWDOWN ____ ______ _________0600200 STEAM GENERATOR 060 LOOP3 716' 8 GENERATO 1.31 0.75 RMI 2.345 0.14 S.S. STD N/A 6" OD INSULATION L 03 LO3 71' 8 BLOWDOWN ______ ____ ___0600200 LOOP3 716' 8 STEAM GENERATOR 1.31 1.11 RMI 3.345 0.38 S.S. STD N/A 8" OD INSULATION L 03 BLOWDOWN 0600200 LOOPSTEAM GENERATOR 2.88 0.28 RMI 2.06 0.06 S.S. STD N/A 7" OD INSULATION L 03 BLOWDOWN N/A LOOP 4 716' 9 STEAM GENERATOR SEE CALC RMI SEE CALC 215.60 S.S. STD N/A N/A A SEE CALC N/A LOOP 4 716' 9 STEAM GENERATOR SEE CALC RMI SEE CALC 0.58 S.S. STD N/A AT ROOT VALVES A CALC 0600200 06 LOOP 4 716' 9 FEEDWATER 16.00 20.07 RMI 2.5 20.25 S.S. STD N/A 21" OD INSULATION B 0600200 LOOP 4 716' 9 FEEDWATER 16.00 6.78 RMI 0.5 1.22 S.S. STD N/A 17" OD INSULATION B 04 0600200 SEE LOOP 4 716' 9 FEEDWATER SEE CALC RMI SEE CALC 0.35 S.S. STD N/A AT 1.88" OD LINE B 04 CALC 0600200 SEE LOOP 4 716' 9 FEEDWATER SEE CALC RMI SEE CALC 0.14 S.S. STD N/A AT 1" LINE B 04 CALC I 0600200 LOOP4 716' 9 FEEDWATER 30.25 0.50 MINERAL 2 0.70 N/A STD N/A AT PENETRATION

X-12D B LOP4 76094EWTR 02 .0 WOOL N/A LOOP 4 716t 9 HOT LEG SEE CALC RMI SEE CALC 72.51 S.S. STD N/A N/A C CALC SEE N/A LOOP 4 716' 9 COLD LEG SEE CALC RMI SEE CALC 54.86 S.S. STD N/A N/A D CALC 0600200 LOOP4 716' 9 BORON INJECTION 1.90 4.45 RMI 2.55 1.10 S.S. STD N/A 7" OD INSULATION E 05 1 0600200 LOOP4 716' 9 BORON INJECTION 1.90 0.90 RMI 7.6 1.42 S.S. STD N/A 9.5" OD INSULATION E 05 0600200 4 716' 9 ACCUMULATOR 10.75 26.25 RMI 3.125 24.83 S.S. STD N/A 17" OD INSULATION F 01 INJECTION 0600200 LOOPACCUMULATOR 10.75 5.42 RMI 9.625 23.19 S.S. STD N/A 30" OD INSULATION F 01 INJECTION I

ALION-CAL-TVA-2739-03 Revision 3 Attachment A 12 of 25 WATTS BAR NUCLEAR PLANT UNIT I WALK DOWN RESULTS INSUL. PCE PROBLEM LOCATION ELEV. AREA DESCRIPTION OD LENGTH INSUL. INSULATION VOLUME JACKET BUCKLE STRAP COMMENTS PACKET NUMBER (IN) (FT) TYPE THICKNESS (IN)MATERIAL TYPE TYPE LETTER 0600200-09 LOWHEAD_____________(T3AMTEILEYPTTP 0600200 LOOP 4 716' 9 LOWHEAD SAFETY 6.63 7.04 RMI 1.1875 1.43 S.S. STD N/A 9" OD INSULATION G 01 INJECTION N/A LOOP 4 720-737 9 LABELS AND TIE WRAPS N/A N/A N/A N/A N/A N/A N/A N/A SEE REPORT FOR H I_ I COMMENTS N/A LOOP 4 720-737 9 RTV SEALANT N/A N/A N/A N/A N/A N/A N/A N/A N/A J 0600200 STEAM GENERATOR 04 LOOP4 716' 9 BLOWDOWN 3.50 35.25 RMI 2.25 9.95 S.S. STO N/A 8" OD INSULATION K 0600200 STEAM GENERATOR 0 -LOOP- 4 716' 9 GENERATO 4.50 36.84 RMI 2.25 12.21 S.S. STD N/A 9" OD INSULATION K 04 BLOWDOWN 0600200 LOOPSTEAM GENERATOR 4.50 0.79 RMI 1.25 0.12 S.S. STD N/A 7" OD INSULATION K 04 BLOWDOWN 0600200 STEAM GENERATOR LOOP 4 716' 9 BLOWDOWN 1.32 0.75 RMI 2.84 0,42 S.S. STD N/A _T'OD INSULATION K 0600200 LOP 1' 9 STEAM GENERATOR 1.32 0.759 RMI 2.34 0.14 S.S. STD N/A 6" 00 INSULATION K 04 BLOWDOWN 0600200 STEAM GENERATOR LOOP 4 716' 9 1.32 0.35 RMI 2.34 0.10 S.S. STD N/A 8" OD INSULATION K 04 BLOWDOWN 0600200 STEAM GENERATOR 0 0 LOOP 4 716' 9 3" ALTERNATE CHARGING 3.50 65.75 RMI 2.75 24.65 S.S. STD N/A 9 OD INSULATION L 0600200 LOOP 4 716' 9 3" ALTERNATE CHARGING 3.50 2.34 RMI 2.25 0.66 S.S. STD N/A 8" OD INSULATION L 0600200 1"0 NUAINA 11 LOOP 4 716' 9 3" ALTERNATE CHARGING 3.50 2.91 RMI 6.75 4.39 S.S. STD N/A " OD INSULATION A L 11 1VALVES 0600200 LOOP 1 745' 10 MAIN STEAM 32.00 63.17 RMI 3.5 171.24 S.S. STD N/A N/A A 01 1 0600200 LOOP 1 745' 10 MAIN STEAM -32.00 3.55 MIN-K 6 17.66 S.S. N/A N/A NEAR PENETRATION A-011 0600200 LOOP 1 745' 10 MAIN STEAM 32.00 2.83 MIN-K 1.5 3.10 S.S. N/A N/A NEAR TOP OF SG A 01 0600200 SEE 01 LOOP 1 745' 10 MAIN STEAM CALC SEE CALC RMI SEE CALC 1.48 S.S. STD N/A AT 1" VENT LINE A 0600200 SEE AT 1" INSTRUMENT TEST LOOP 1 745' 10 MAIN STEAM SEE CALC RMI SEE CALC 0.34 S.S. STD N/A A 01 _________

CALC ____LINE 0600200 SEE AT 3/4" INSTRUMENT LOOP 1 745' 10 MAIN STEAM SEE CALC RMI SEE CALC 1.34 S.S. STO N/A TEST LINESA 01 ___ _________CALC TEST_____

LINES___SEE N/A LOOP 1 745' 10 STEAM GENERATOR SEE CALC RMI SEE CALC 451.03 S.S. STD N/A N/A B CALC 0600200 LOOP 1 745' 10 AUXLILIARY FEEDWATER 6.63 3.17 RMI 5.1875 4.24 S.S. STO N/A 17" OD INSULATION C 0600200 LOOP 1 745' 10 AUXLILIARY FEEDWATER 6.63 5 9.00 RMI 2.6875 32.21 S.S. STO N/A 12" 00 INSULATION C 05 0600200 LOOP 1 745' 10 AUXLILIARY FEEDWATER 6.63 3.01 MIN-K 2.8125 1.74 S.S. STD N/A 12.25" OD INSULATION C 05 0600200 LOOP 1 745' 10 AUXLILIARY FEEDWATER 6.63 1.43 RMI 1.6875 0.44 S.S. STD N/A 10" OD INSULATION C 05 1 ALION-CAL-TVA-2739-03 Revision 3 Attachment A 13 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS INSUL. PCE PROBLEM OD LENGTH INSUL. INSULATION VOLU JACKET BUCKLE STRAP PACKET NUMBER LOCATION ELEV. AREA DESCRIPTION (IN) (FT) TYPE THICKNESS (IN) VOLUME COMMENTS (FT3) LETTER 0600200 LOOP 1 745' 10 AUXLILIARY FEEDWATER 1.31 1.20 RMI 2.845 0.31 S.S. STD N/A AT 1.31" OD LINE C 05 N/A LOOP 1 745' 10 SEAL AROUND HVAC N/A N/A N/A N/A N/A N/A N/A N/A N/A D DIFFUSER N/A LOOP 1 745' 10 CONDUIT INSULATION 3M 1.90 5.00 3M20C SEE CALC 0.22 N/A N/A N/A SEE CALCULATION E RADIANT I N/A LOOP 1 745' 10 JUNCTION BOX N/A N/A 3M20C SEE CALC 0.26 N/A N/A N/A SEE CALCULATION E N/A LOOP 1 745' 10 SUPPORT N/A N/A 3M20C SEE CALC 0.26 N/A N/A N/A SEE CALCULATION E 0600200 LOOP 2 745' 11 MAIN STEAM 32.00 67.50 RMI 3.5 182.97 S.S. STO N/A N/A A 02 LOOP 2 745' 11 MAIN STEAM 32.00 2.75 MIN-K 1.5 3.01 S.S. N/A N/A NEAR TOP OF SG A 02 LOOP 2 745' 11 MAIN STEAM SEE CALC RMI SEE CALC 1.63 S.S. STD N/A AT 1" VENT LINE A 02 CALC ILINE 0600200 SEE AT 1" INSTRUMENT TEST LOOP 2 745' 11 MAIN STEAM SEE CALC RMI SEE CALC 0.37 S.S. STD N/A A 02 ___ __CALC LINE 0600200 SEE AT 3/4" INSTRUMENT LOOP 2 745' 11 MAIN STEAM SEE CALC RMI SE. CALC 1.41 S.S. STD N/A A 02 CALC ____________

____ TEST LINES ____N/A LOOP 2 745' 11 STEAM GEERATOR SEE CALC RMI SEE CALC 451.03 S.S. STD N/A N/A B N/AOOP__745 11__ SEMGNRTR CALC ____0600200 LOOP 2 745' 11 AUXLILIARY FEEDWATER 6.63 3.50 RMI 5.1875 4.68 S.S. STD N/A 17" OD INSULATION C 02 T600200 02 LOOP 2 745' 11 AUXLILIARY FEEDWATER 6.63 2.28 RMI 3.6875 1.89 S.S. STD N/A 14" OD INSULATION C 0600200 0600200 LOOP 2 745' 11 AUXLILIARY FEEDWATER 6.63 50.72 RMI 2.6875 27.69 S.S. STD N/A 12" OD INSULATION C 02 0600200 LOOP 2 745' 11 AUXLILIARY FEEDWATER 6.63 2.10 RMI 1.6875 0.64 S.S. STD N/A 10" OD INSULATION C 02 0600200-0S-LOOP 2 745' 11 AUXLILIARY FEEDWATER 6.63 2.44 MIN-K 0.3775 0.14 S.S. STD N/A 7.38" OD INSULATION C 02 0600200 LOOP 2 745' 11 AUXLILIARY FEEDWATER 6.63 15.09 RMI 2.6875 8.24 S.S. STD N/A 12" OD INSULATION E 02 0600200 LOOP 2 745' 11 AUXLILIARY FEEDWATER 4.50 26.09 RMI 2.75 11.35 S.S. STD N/A 10" OD INSULATION E 02 0600200 LOOP 2 745' 11 AUXLILIARY FEEDWATER 4.50 2.84 RMI 6.75 4.71 S.S. STD N/A 18" 00 INSULATION A 03 0600200 LOOP 2 745' 11 AUXLILIARY FEEDWATER 1.31 0.45 RMI 2.345 0.08 S.S. STD N/A 6" 00 INSULATION E 0020O- LOOP 2 745' 11 AUXLILIARY FEEDWATER 1.31 1.11 RMI 2.847 0.29 S.S. STD N/A 7' 00 INSULATION E 03 00200- LOOP 3 745' 12 MAIN STEAM 32.00 66.70 RMI 3.5 180.80 S.S. STD N/A N/A A 00200- LOOP 3 745' 12 MAIN STEAM 32.00 3.10 MIN-K 1.5 3.40 S.S. N/A N/A NEAR TOP OF SG A 0600200 LOOP 3 745' 12 MAIN STEAM SEE CALC RMI SEE CALC 1.42 S.S. STD N/A AT 1" VENT LINE A 03 1 CALC ALION-CAL-TVA-2739-03 Revision 3 Attachment A 14 of 25 WATTS BAR NUCLEAR PLANT UNIT I WALK DOWN RESULTS PROBLEM LOCATION ELEV. AREA DESCRIPTION OD LENGTH INSUL. INSULATION VOLUMEL JACKET BUCKLE STRAP CKETT NUMBER (IN) (FT) TYPE THICKNESS (IN) (FT3M MATERIAL TYPE TYPE COMMENTS LETTER_________

_________________

___________ (FT3) MTRA YE TP 0600200 SEEAT1INRUETES LOOP 3 745' 12 MAIN STEAM SEE CALC RMI SEE CALC 0.38 S.S. STD N/A AT 1" INSTRUMENT TEST A 03 CALC LINE S0600200 SEE AT 3/4" INSTRUMENT LOOP 3 745' 12 MAIN STEAM SEE CALC RMI SEE CALC 1.35 S.S. STD N/A A 03 CALC TEST LINES N/A LOOP3 745 12 STEAM GENERATOR SEE CALC RMI SEE CALC 451.03 S.S. STD N/A N/A B GALE 1____0600200 LOOP 3 745' 12 AUXLILIARY FEEDWATER 6.63 3.50 RMI 5.1875 4.68 S.S. STD N/A 17" OD INSULATION C 01 T600200 LOOP 3 745' 12 AUXLILIARY FEEDWATER 6.63 2.67 RMI 3.6875 2.22 S.S. STD N/A 14" OD INSULATION C 01 0600200 LOOP 3 745' 12 AUXLILIARY FEEDWATER 6.63 48.70 RMI 2.6875 26.59 S.S. STD N/A 12" OD INSULATION C 01 0600200 LOOP 3 745' 12 AUXLILIARY FEEDWATER 6.63 3.00 RMI 1.6875 0.92 S.S. STD N/A 10" OD INSULATION C 01 0600200 LOOP 3 745' 12 AUXLILIARY FEEDWATER 6.63 1.92 RMI 0.6875 0.21 S.S. STD N/A 8" OD INSULATION C 01 0600200 LOOP 3 745' 12 AUXLILIARY FEEDWATER 6.63 18.50 RMI 2.6875 10.10 S.S. STD N/A 12" OD INSULATION D 01 0600200 LOOP 3 745' 12 AUXLILIARY FEEDWATER 4.50 20.50 RMI 2.75 8.92 S.S. STD N/A 10"OD INSULATION D 01 0600200-OS-LOOP 3 745' 12 AUXLILIARY FEEDWATER 4.50 1.72 RMI 1.75 0.41 S.S. STD N/A 8"OD INSULATION D 0111 0600200 LOOP 3 745' 12 AUXLILIARY FEEDWATER 4.50 3.32 RMI 7.25 6.17 S.S. STD N/A 19"OD INSULATION D 011 0600200 LOOP 3 745' 12 AUXLILIARY FEEDWATER 1.31 2.18 RMI 2.345 0.41 S.S. STD N/A 6" OD INSULATION D 01 1 N/A LOOP 4 745' 13 DUST BETWEEN GRATING N/A N/A N/A N/A N/A N/A N/A N/A N/A A 0600200 LOOP 4 745' 13 MAIN STEAM 32.00 63.09 RMI 3.5 171.02 S.S. STD N/A N/A B 04 0600200 LOOP 4 745' 13 MAIN STEAM 32.00 3.51 MIN-K 6 17.46 S.S. N/A N/A NEAR PENETRATION B 04 0600200 LOOP 4 745' 13 MAIN STEAM 32.00 3.17 MIN-K 1.5 3.48 S.S. N/A N/A NEAR TOP OF SG B 04 0600200 LOOP 4 745' 13 MAIN STEAM SEE CALC RMI SEE CALC 1.45 S.S. STD N/A AT 1" VENT LINE B 04 CALC 0600200 SEE AT 1" INSTRUMENT TEST LOOP 4 745' 13 MAIN STEAM SEE CALC RMI SEE CALC 0.35 S.S. STD N/A B 04 CALC LINE 0600200 SEE AT 3/4" INSTRUMENT LOOP 4 745' 13 MAIN STEAM SEE CALC RMI SEE CALC 1.13 S.S. STD N/A B 04 CALC I TEST LINES N/A LOOP 4 745' 13 STEAM GENERATOR SEE SEE CALC RMI SEE CALC 451.03 S.S. STD N/A N/A C 680200-02AL-0600200 LOOP 4 745' 13 AUXLILIARY FEEDWATER 6.63 3.34 RMI 5.1875 4.47 S.S. STD N/A 17" OD INSULATION

)0600200 LOOP 4 745' 13 AUXLILIARY FEEDWATER 6.63 49.20 RMI 2.6875. 26.86 S.S. STD N/A 12" OD INSULATION 0 08 1 1 ALI ON-CAL-TVA-2739-03 Revision 3 Attachment A 15 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM OD LENGTH INSUL. INSULATION JACKET SUCKLE STRAP PACKET LOCATION ELEV. AREA DESCRIPTION 00 LENG TH INSUAIN VOLUME JACET BUKE TRP COMMENTS LETTER NUMBER (IN) (FT) TYPE THICKNESS (IN) (F3 MAEIL TP TYEETR 6020-2(FT3)

M 06002002-LOOP 4 745' 13 AUXLILIARY FEEDWATER 6.63 3.01 MIN-K 2.8125 1.74 S.S. STD N/A 12.25" OD INSULATION D 08 060020 LOOP 4 745' 13 AUXLILIARY FEEDWATER 6.63 1.18 RMI 1.6875 0.36 S.S. STD N/A 10" OD INSULATION D 08 1______ 1___ 1 1____060020-02-SEE 0600200-02-8 LOOP 4 745' 13 AUXLILIARY FEEDWATER CALC SEE CALC RMI SEE CALC 0,43 S.S. STD N/A AT 1" PIPE D N/A LOOP 4 745' 13 LABELS AND TIE WRAPS N/A N/A N/A N/A N/A N/A N/A N/A SEE REPORT FOR E COMMENTS N/A LOOP 4 745' 13 CONDUIT INSULATION 3M 1.90 2.50 3M20C SEE CALC 0.08 N/A N/A N/A SEE CALCULATION F RADIANT________

N/A LOOP 4 745' 13 SUPPORT N/A N/A 3M20C SEE CALC 0.26 N/A N/A N/A SEE CALCULATION F N/A FAN ROOM 1 716' 14 MIN-K-WR N/A SEE CALC MIN-K-WR 0.25 0.02 N/A N/A N/A ENCAPSULATED IN A I_ STAINLESS FOIL ENCAPSULATED IN N/A FAN ROOM 1 716' 14 MIN-K-WR N/A SEE CALC MIN-K-WR 0.375 0.02 N/A N/A N/A B STAINLESS FOIL N/A FAN ROOM 1 716' 14 MIN-K-WR N/A SEE CALC MIN-K-WR 0.375 0.04 N/A N/A N/A ENCAPSULATED IN C STAINLESS FOIL N/A FAN ROOM 1 716' 14 MIN-K-WR N/A SEE CALC MIN-K-WR 0.5 0.03 N/A N/A N/A ENCAPSULATED IN D STAINLESS FOIL ENCAPSULATED IN N/A FAN ROOM 1 716' 14 MIN-K-WR N/A SEE CALC MIN-K-WR SEE CALC 0.24 N/A N/A N/A F STAINLESS 0600200-07-FAN ROOM 1 716' 14 4.50 23.92 RMI 2.25 7.93 S.S. STD N/A 9" OD INSULATION G 04 BLOWDOWN 0600200 STEAM GENERATOR 14' OD INSULATION G FAN ROOM 1 716' 14 BLEWDOWN 4.50 1.34 RMI 4.75 1.28 S.S. STD N/A 1 VALV)NSUATION G 04 BLOWDOWN (VALVE)0600200 STEAM GENERATOR 16" OD INSULATION G FAN ROOM 1 716' 14 SLOWDOWN 11.75 1.59 RMI 2.125 1.02 S.S. STD N/A 1 FLANI)G 04 BLOWDOWN (FLANGE)0600200 FAN ROOM 1 716' 14 STEAM GENERATOR 4.50 1.55 RMI 4.25 1.26 D N/A 13" OD INSULATION G 04 BLOWDOWN S.S. ST (VALVE)0600200 STEAM GENERATOR 9" OD INSULATION FAN ROOM 1 716' 14 LOWDOWN 2.38 1.96 RMI 3.31 0.81 S.S. STD N/A (VALVE) G 0600200 FA OM1 76 4 STEAM GENERATOR 060 R00- OTA GENERAT 2.38 0.40 RMI 12.5 1.62 S.S. STD N/A T' OD INSULATION G FA0OO4 16 4 BLOWDOWN_____________

0600200 STEAM GENERATOR 13" 00 INSULATIONG FAN ROOM 1 716' 14 BLEWM OWN 8.62 0.64 RMI 2.19 0.33 S.S. STD N/A G 04 BLOWDOWN (FLANGE)0600200 FAN ROOM 1 716' 14 STEAM GENERATOR 4.50 2.85 MIN-K 1.5 0.56 S.S. STD N/A 7.5" OD INSULATION G 04 BLOWDOWN I N/A FAN ROOM 1 716' 14 CONDUIT INSULATION 3M 1.32 40.00 3M20C SEE CALC 1.34 N/A N/A N/A SEE CALCULATION H RADIANT N/A FAN ROOM 1 716' 14 SUPPORT N/A N/A 3M20C SEE CALC 0.64 N/A N/A N/A SEE CALCULATION H N/A FAN ROOM 1 716' 14 BOX N/A N/A 3M20C SEE CALC 2.08 N/A N/A N/A SEE CALCULATION H 0600200 FAN ROOM 1 716' 14 ESAFETY 6.63 54.00 RMI 2.6875 29.48 S.S. STD N/A 12" OD INSULATION J 01 FA OM1 76 4 INJECTION

__________

0600200 LOWHEAD SAFETY 06 0 FAN ROOM 1 716' 14 1.05 0.43 RMI 0.975 0.02 S.S. STD N/A 3" OD INSULATION J 01 FA OM1 76 4 INJECTION

____ ________________

______________

0600200-09-FAN ROOM 1 716 14 1.05 0.34 RMI 1.475 0.03 S.S. STD N/A 4" OD INSULATION J 01 INJECTION ALION-CAL-TVA-2739-03 Revision 3 Attachment A 16 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS INSUL. JCE UKE SRPPCE PROBLEM OD LENGTH INSUL. INSULATION JACKET BUCKLE STRAP PACKET LOCATION ELEV. AREA DESCRIPTION VOLUME COMMENTS NUMBER (IN) (FT) TYPE THICKNESS (IN) (FT3) MATERIAL TYPE TYPE LETTER 0600200 FAN ROOM 1 716' 14 LOWHEAO SAFETY 2.38 0.63 RMI 0.81 0.04 S.S, STD N/A 4" OD INSULATION J 01 INJECTION N/A FAN ROOM 1 716' 14 MIN-K-WR N/A SEE CALC MIN-K-WR 0.5 0.02 N/A N/A N/A ENCAPSULATED IN K I I__I__I STAINLESS FOIL N/A FAN ROOM 1 716' 14 RESIDUAL HEAT 8.63 49.84 RMI 1.1875 12.67 S.S. STD N/A 1100 INSULATION L N/A FAN ROOM 1 716' 14 RESIDUAL HEAT 8.63 49.84 RMI 1.1875 12.67 S.S. STD N/A 11" OD INSULATION M REMOVAL N/A FAN ROOM 1 716' 14 RESIDUAL HEAT 8.63 1.72 MIN-K 0.9375 0.34 S.S. STD N/A 10.5' 00 MIN-K M_______REMOVAL____

____ INSULATION

____0600200 FAN ROOM 1 716' 14 LOWHEAD SAFETY 8.63 44.60 RMI 1.1875 11.34 S.S. STD N/A 11" OD INSULATION N 0FAN ROOM 1 716' 14 LOWHEAD SAFETY 8.63 1.98 MIN-K 0.56 0.22 S.S. STO N/A 9.750O INSULATION N INECTONA INUATO 02 FAN ROOM 1 716' 14 LOWHEAD SAFETY 8.63 2.50 RMI 0.6875 0.35 S.S. STD N/A 10" OD INSULATION N 02 INJECTION 0600200 FAN ROOM 1 716' 14 STEAM GENERATOR 4.50 30.09 RMI 2.25 9.97 S.S. STD N/A 900 O INSULATION P 01 ___ __ LOWDOWN_____

0600200 STWEAM GENERTOR 06 FAN ROOM 1 716' 14 STEAMG N 4.5 1.04 RMI 1.75 0,25 S.S. STD N/A 5" OD INSULATION P 0600200 STEAM GENERATOR 01 FAN ROOM 1 716' 14 8LOWDOWN .5 1.8 MI 1.25 0, S.S. STD N/A 10"_OD INSULATION N 0600200-07-FAN ROOM 1 716' 14 4.50 1.28 RMI 4.75 1.23 S.S. STD N/A 14" OD INSULATION P 01 BLOWDOWN 0600200 STEAM GENERATOR 1600 INSULATION 01 FAN ROOM 1 716' 14 BLOWDOWN 11.50 1.50 RI 22 .1 S T / (FLANGES)0600200 FAN ROOM 1 716' 14 STEAM GENERATOR 4.50 1.57 RMI 4.25 1.27 S.S. STD N/A 13" OD INSULATION P 01 BLOWDOWN 0600200 STEAM GENERATOR 1.79 RMI 3.31 0.74 6.5. STD N/A 900 INSULATION P 01 FA OM1 1' 1 LOWDOWN_______

0600200-07-FAN ROOM 1 716' 14 2.38 1.33 RMI 2.31 0.31 S.S. STD N/A 7" OD INSULATION P 01 BLOWDOWN 0600200 STEAM GENERATOR13ODISLTN 06 FAN ROOM 1 716' 14 BLOW4OWN 8.62 0.56 RMI 2.19 0.29 S.S. STD N/A 1" 0 INSULATION P 0600200 STEAM GENERATOR (FLANS)LATION 06 0 FAN ROOM 1 716' 14 GENE O 2.00 0.59 RMI 2.81 0.17 S.S. STD N/A 8" 00 INSULATION P 0600200 STEAM GENERATOR 4.50 1.13 MIN-K 0.56 0.07 S.S. STD N/A 5.620O INSULATION P 01 FA OM1 1' 1 LOWDOWN ____ ______ ___ ______________

0600200-07-FAN ROOM 1 716' 14 4.50 28.42 RMI 2.25 9.42 S.S. STD N/A 9 OD INSULATION a 02 BLOWDOWN 1 0600200-07-FAN ROOM 1 716'STEAM GENERATOR 4.50 1.61 RMI 4.25 1.31 S.S. STD N/A 13" OD INSULATION a 02 M BLOWDOWN 0600200 STEAM GENERATOR 02 FAN ROOM 1 716' 14 LOWDOWN .1.3 RMI 4. .31 S.S. STD N/A 1" OD INSULATION Q 0600200 STEAM GENERATOR 4.50 20.00 RMI 2.25 F 663 S.S. STD N/A 9OD INSULATION R 03 FAN ROOM 1 716' 14 8MLOWDOWN I_ I_ _ _ _ _ 29 SS. STD N/A P ALI ON-CAL-TVA-2739-03 Revision 3 Attachment A 17 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM OD LENGTH INSUL INSULATION INSUL. JACKET BUCKLE STRAP PACKET NUMBER LOCATION ELEV. AREA DESCRIPTION (IN) (FT) TYPE THICKNESS (IN) VOLUME JACET BUKE TRP COMMENTS LETTER LOCATION) (T) TPE TICKESS IN) (FT3) MATERIAL TYPE TYPE 0600200 FAN ROOM 1 716' 14 STEAM GENERATOR 4.50 0.50 RMI 1.25 0.08 S.S. STD N/A 7" OD INSULATION R 03 BLOWDOWN 60320-7 STEAM GENERATOR 14" GD INSULATION R 0600200 FAN ROOM 1 716' 14 BLEA DWN 4.50 1.34 RMI 4.75 1.28 S.S. STD N/A 1 VALV)R 03 BLOWDOWN I-(VALVE)0600200 STEAM GENERATOR 1.55 RMI 4.25 1.26 SS STD N/A 13" OD INSULATION R FAN ROOM 1 716' 14 BL.5DWN 1.55_ _M___.25_.26_S S. STDN/A_03 BLOWDOWN (VALVE)ENCAPSULATED IN N/A FAN ROOM 2 716' 15 MIN-K-WR N/A SEE CALC MIN-K-WR 0.5 0.02 N/A N/A N/A ST LES I A STAINLESS FOIL N/A FAN ROOM 2 716 15 MARINITE BOARD N/A SEE CALC MARINITE 1 0.03 N/A N/A N/A N/A A 0600200-09-FAN ROOM 2 716' 15 6.63 46.09 RMI 1.1875 9.33 S.S. STD N/A 9" OD INSULATION B 02 INJECTION I 0600200.09-FAN ROOM 2 716' 15 LOWHEAD SAFETY 6.63 2.25 RMI 0.6875 0.25 S.S. STD N/A 800 INSULATION B 02 INJECTION 6._N8 SA 0600200-09-FAN ROOM 2 716' 15 6.63 0.85 MIN-K 1.1875 0.17 S.S. STD N/A 9" OD MIN-K INSULATION B 02 INJECTION N/A FAN ROOM 2 716' 15 CONDUIT INSULATION 3M 2.38 47.50 3M20C SEE CALC 2.48 N/A N/A N/A SEE CALCULATION C RADIANT N/A FAN ROOM 2 716' 15 SUPPORT N/A N/A 3M20C SEE CALC 0.77 N/A N/A N/A SEE CALCULATION C N/A FAN ROOM 2 716' 15 BOX N/A N/A 3M20C SEE CALC 2.08 N/A N/A N/A SEE CALCULATION C 0600200-07-FAN ROOM 2 716' 15 4.50 11.75 RMI 2.25 3.89 S.S. STD N/A 9" OD INSULATION D 02 BLOWDOWN 0600200 STEAM GENERATOR 02 FAN ROOM 2 716' 15 2.38 1.66 RMI 2.31 0.39 S.S. STD N/A "OD INSULATION D 0600200 STEAM GENERATOR 2.38 1.66 RMI 2.31 0.39 S.S. STD N/A 7' 00 INSULATION E FA0OM231' 1 BLOWDOWN ____ ___FAN ROOM 2 716' 15 STEAM GENERATOR 4.50 11.05 RMI 2.25 3.66 S.S. STD N/A 9" OD INSULATION E 03 BLOWDOWN FAN ROOM 2 716' 15 GENERATOR 2.38 0.82 RMI 2.31 0.19 S.S. STD N/A 7" OD INSULATION E FR 2 'BLOWDOWN 060020 MSEAM7GEERATOR 2.38 0.59 RMI 2.81 0 .19 S.S. STO N/A 8" 00 INSULATION E FA0OO3 16 5 BLOWDOWN__________________

N/A FAN ROOM 2 716' 15 MIN-K N/A N/A MIN-K 0.505 0.03 N/A N/A N/A N/A F N/A MULTCSEE REPORT FOR A N/A ACCUMULATO 716' 16 TAGS & LABELS N/A N/A N/A N/A N/A N/A N/A N/A COM TSA R ROOM 1 1 COMMENTS ACCUMULATe SEE REPORT FOR PAINT N/A R ROO 716' 16 POTENTIAL PAINT CHIPS N/A N/A N/A N/A N/A N/A N/A N/A ISU RB R ROOM 1 1ISSUE ACCUMULATO SEE SEE SEE SEE SEE SEE WB1-DWD-014D, -N/A RAROOMU1 716' 16 MIRROR INSULATIONS COMM SEECOMMENT COMMENT N/A N/A 014E-16F&-16GC I ENT COMMENT COMMENT N/A-N/A 0600200 ACCUMULATO LOWHEAD SAFETY 6.63 16.24 RMI 2.6875 8.87 S.S. STD N/A 12" OD INSULATION D 01 R ROOM 1 INJECTION 1 0600200 ACCUMULATO LOWHEAD SAFETY 6.63 2.17 RMI 8.6875 6.30 S.S. STD N/A 24" OD INSULATION D 01 R ROOM 1 INJECTION 0600200 ACCUMULATO LOWHEAD SAFETY 2.38 8.16 RMI 2.3125 1.93 S.S. STD N/A 7" OD INSULATION D 01 R ROOM 1 INJECTION 1 0600200 ACCUMULATO LOWHEAD SAFETY 1.05 0.43 RMI 1.8125 0.05 S.S. STD N/A 6" OD INSULATION D 01 R ROOM 1 1 1 INJECTION I , I I I ALION-CAL-TVA-2739-03 Revision 3 Attachment A 18 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM ~INSUL. PCE PROBLEM LOCATION ELEV. AREA DESCRIPTION OD LENGTH INSUL. INSULATION VOLU JACKET BUCKLE STRAP PACKET NUMBER (IN) (FT) TYPE THICKNESS (IN) VFL3) MATERIAL TYPE TYPE LETTER 0600200 ACCUMULATO LOWHEAD SAFETY 1.05 0.84 MIN-K 0.25 0.01 .5. STD N/A .25" THK. MIN-K 01 R ROOM 1 INJECTION INSULATION 0600200 ACCUMULATO 716' 16 LOWHEAD SAFETY 1.05 0.40 MIN-K 2.2 0.06 S.S. STD N/A 3.25" OD MIN-K D 01 R ROOM 1 INJECTION INSULATION N/A 716'RESIDUAL HEAT 8.63 19.92 RMI 1.1875 5.06 S.S. STD N/A 11" OD INSULATION E R ROOM 1 REMOVAL ACCUMULATO 76 16 REMOVUAL ___EAT_____

N/A 716'RESIDUAL HEAT 8.63 2.25 RMI 5.69 4.00 S.S. STD N/A 20" 00 INSULATION E ACCUMULATO 76 16 REMOVUAL HEAT______

R_ _ RROOM 1 REMOVAL_ ___N/A 716'RESIDUAL HEAT 8.63 2.64 RMI 1.6875 1.00 S.S. STD N/A 12" OD INSULATION E R ROOM 1 REMOVAL N/A 716'RESIDUAL HEAT 2.38 4.50 RMI 1.31 0.47 S.S. STD N/A 5" OD INSULATION E ACCUMULATO 76 16 REMODUAL HEAT___ ____R ROOM_1 REMOVAL___________

____N/A 716'RESIDUAL HEAT 2.38 0.88 RMI 2.31 0.21 S.S. STD N/A 7" OD INSULATION E R ROOM t REMOVAL N/A ACCUMULATO RESIDUAL HEAT 1.06 0.71 RMI 2.47 0.14 S.S. STD N/A 6" OD INSULATION E R ROOM1 __ 1 REMOVAL N/A ACCUMULATO 716' 16 RESIDUAL HEAT 8.63 14.56 RMI 1.1875 3.70 S.S. STD N/A 11" OD INSULATION F R ROOM 1 REMOVAL 06600200 ACCUMULATO LOWHEA SAFETY 8.63 16.92 RMI 1.1875 4.30 S.S. STD N/A 11" OD INSULATION G 02 R ROOM 1 INJECTION 0600200 ACCUMULATO 716' 17 3" AUXILIARY SPRAY LINE 3.50 1.28 RMI 1.25 0.17 S.S. STD N/A 6" OD INSULATION A 02 R ROOM 2 0600200 ACCUMULATO 716' 17 3" AUXILIARY SPRAY LINE 3.50 22.91 RMI 2.75 8.59 S.S. STD N/A 9" OD INSULATION A 02 R ROOM 2 0600200 ACCUMULATO 716' 17 3" AUXILIARY SPRAY LINE 3.50 0.66 MIN-K 1.5 0.11 S.S. STD N/A 6.5" OD INSULATION A 02 R ROOM 2 0600200 ACCUMULATO 716' 17 3" AUXILIARY SPRAY LINE 3.50 1.09 RMI 4.25 0.78 S.S. STD N/A 12" OD INSULATION A 02 R ROOM 2 0600200 ACCUMULATO LOWHEA0 SAFETY 6.63 18.42 RMI 1.1875 3.73 S.S. STD N/A 9OD INSULATION B 02 R ROOM 2 INJECTION 1 0600200 ACCUMULATO LOWHEAD SAFETY 6.63 1.92 RMI 6.6875 3.73 S.S. STD N/A 20"OD INSULATION B 02 R ROOM 2 INJECTION 060]0200 ACCUMULATO 1 LOWHEAD SAFETY 02 ACCUMULT 716' 17 L NJEAO 8.63 13.59 RMI 1.1875 3.45 S.S. STD N/A 11" OD INSULATION B 0600200 ACCUMULATO 76 17 LOWHEAO SAFETY 2.38 1.34 MIN-K 0.8125 0.08 S.S. STD N/A 400O MIN-K INSULATION 8 02 RROOM2 INJECTION I 0600200 ACCUMULATO LOWHEAD SAFETY 2.38 0.78 RMI 0.5625 0.03 S.S. STD N/A 3.5" OD INSULATION B 02 R ROOM 2 INJECTION 0600200 ACCUMULATO LOWHEAD SAFETY 3"0 I-716' 17 2.38 0.92 MIN-K 0.5625 0.03 S.S. STD N/A 3.5" OD INS-K B 02 R ROOM 2 INJECTION INSULATION 0600200 ACCUMULATO LOWHEAO SAFETY 2.38 0.50 MIN-K 1.3125 0.05 S.S. STD N/A 500 MIN-K INSULATION B 02 R ROOM 2 INJECTION INSULATION 0600200 ACCMULATO

'LOWHEAD SAFETY 2.38 4.9 RMI 1.3125 0.45 S.S. STD N/A 5OD INSULATION B 02 R ROOM 2 INJECTION I _ 1 0600200 ACCUMULATO LOWHEAD SAFETY 2.38 10.00 RMI 2.3125 2.36 S.S. STD N/A T7OD INSULATION B 02 R ROOM 2 INJECTION

_ I I ALI ON-CAL-TVA-2739-03 Revision 3 Attachment A 19 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM OD LENGTH INSUL. INSULATION INSUL. JACKET BUCKLE STRAP PACKET PROBEM LOCATION ELEV. AREA DESCRIPTION (IN) (FT) TYPE THICKNESS (IN)COMMENTS NUMBER_(IN)_(FT__TYPETHICKNESS (IN) (FT3) MATERIAL TYPETYPELETTER 0600200 ACCUMULATO LOWHEAD SAFETY 2.38 1.15 RMI 3.8125 0.59 S.S. STD N/A 10" OD INSULATION B 02 R ROOM 2 INJECTION 0600200 ACCUMULATO 17 LOWHEAD SAFETY 2.38 1.45 RMI 3.8125 0.75 S.S. STD N/A 8" OD INSULATION B 02 R ROOM 2 INJECTION 0600200 ACCUULAT17 LOWHEADSAFETY 1.05 0.51 RMI 1.475 0.04 S.S. STD N/A 4" OD INSULATION B 02 R ROOM 2 INJECTION 060020009-ACCUMULATO 17 LOWHEADSAFETY 1.05 3.67 RMI 2.975 0.96 S.S. STD N/A 7" OD INSULATION B 02 R ROOM 2 INJECTION N/A ACCUMULATO RESIDUAL HEAT 863 27.84 RMI 1.1875 7.08 S.S. STD N/A 11" OD INSULATION C R ROOM 2 REMOVAL I N/A ACCUMULATO RESIDUAL HEAT 8.63 2.17 RMI 8.6875 7.12 S.S. STD N/A 26" OD INSULATION C R ROOM 2 REMOVAL 0600200 ACCUMULATO 716' 17 NORMAL CHARGING 3.50 3.00 RMI 1.75 0.60 S.S. STD N/A 7" 00 INSULATION 0 I1I R ROOM 2____________

0600200 ACCUMULATO 716' 17 NORMAL CHARGING 3.50 0.65 RMI 1.25 0.08 S.S. STD N/A 6" OD INSULATION D 11 R ROOM 2 0600200 ACCUMULATO 716' 17 NORMAL CHARGING 3.50 0.96 RMI 2.75 0.36 S.S. STD N/A 9OD INSULATION D 11 R ROOM 2 1 1 0600200 ACCUMULATO 716' 17 EXCESS LETDOWN 1.32 11.09 RMI 2.34 2.07 S.S. STD N/A 600 INSULATION E 12 R ROOM 2 __ _______ __ __________

0600200 ACCUMULATO 716' 17 EXCESS LETDOWN 1.32 2.00 RMI 1.84 0.25 S.S. STD N/A 5" OD INSULATION E 12 R ROOM 2 0600200 ACCUMULATO 716' 17 EXCESS LETDOWN 1.05 1.07 RMI 1.975 0.14 S.S. STD N/A 5" OD INSULATION E 12 R ROOM 2 0600200 ACCUMULATO 716' 17 EXCESS LETDOWN 1.05 0.67 RMI 2.975 0.18 S.S. STD N/A 6 VOD INSULATION E 12 R ROOM 2(VLE 0600200 ACCUMULATO!

0 0 ACCUMU2O 716' 17 3"ALTERNATE CHARGING 3.50 11.84 RMI 2.75 4.44 S.S. STD N/A 9"OD INSULATION F 0600200 ACCUMULATO 716' 17 3' ALTERNATE CHARGING 3.50 2.75 RMI 1.25 0.36 S.S. STD N/A 6" OD INSULATION F 11 R ROOM2 2VALVE_0600200 ACCUMULATO 716' 17 3" ALTERNATE CHARGING 3.50 2.34 RMI 2.25 0.66 S.S. STD N/A 8" OD INSULATION E 11 R ROOM 2 00298-ACCUMULATO SERPR O 716' 19 TAGS & LABELS N/A N/A N/A N/A N/A N/A N/A N/A C" O ENSTSOR N/ R ROOM 4 COMMENTS N/A ACCUMULATO 716' 19 TAGS & LABELS N/A N/A N/A N/A N/A N/A N/A N/A SHOW RUBBER GASKETS B 11 R ROOM 4 2 1 ACCUMULATO SEE REPORT FORC N/A 716' 19 TAGS & LABELS N/A N/A N/A N/A N/A N/A N/A N/A COMMENTS FOR_R ROOM 4 COMMENTS ACCUMULATNO POTENTIAL DEBRIS N/A ACCUMUAO 716' 19 PENETRATIONS N/A N/A N/A N/A N/A N/A N/A N/A FROM THESE D RROOM4PENETRATIONS 0600200 ACCUMULATO 716' 19 LETDOWN LINE 2.38 23.17 RMI 1.81 3.83 S.S. STID N/ANAE 09 R ROOM 4 0600200 ACCUMULATO 716 19 LOWHEAD SAFETY 6.63 15.67 RMI 1.1875 3.17 S.S. ST N/A 900 INSULATION F 01 R ROOM 4 TINJECTION I 0600200 ACCUMULATO L1WHEAD SAFETY 6.63 2.17 RMI 9.6875 7.48 S.S. STD N/A 26" OD INSULATION F 01 R ROOM 4 7 19 INJECTION I I I _ I I I _ ____1__

ALION-CAL-TVA-2739-03 Revision 3 Attachment A 20 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM OD LENGTH INSUL. INSULATION INSUL. JACKET BUCKLE STRAP PACKET NUMBER (IN) (FT) TYPE THICKNESS (IN) VOT3) MATERIAL TYPE TYPE LETTER-06002-0-09-ACCUMATOT3)

MATRIAL TYPE TYP 0600200 ACCUMULATO LOWHEAD SAFETY 8.63 35.09 RMI 1.1875 8.92 S.S. STD N/A 11" OD INSULATION F 01 R ROOM 4 INJECTION 0600200 ACCUMULATO LOWHEAD SAFETY 8.63 0.53 RMI 2.8187 0.37 S.S. STD N/A 13" OD INSULATION F 01 R ROOM 4 INJECTION 0600200 ACCUMULATO 19 LOWHEAD SAFETY 1.05 8.92 RMI 2.475 1.70 S.S. STD N/A 6" OD INSULATION F 01 R ROOM 4 INJECTION 1 0600200 ACCUMULATO LOWHEAD SAFETY 090 MIN-K 0.726 0.03 S.S. STD N/A 2.5" OD MIN-K F 01 R ROOM 4 INJECTION INSULATION 0600200 ACCUMULATO 716' 19 LOWHEAD SAFETY 1.05 0.94 RMI 3.475 0.32 S.S. STD N/A 8" OD INSULATION F 01 R ROOM 4 INJECTION 0600200 ACCUMULATO 19 LOWHEADSAFETY 2.38 6.25 RMI 2.31 1.48 S.S. STD N/A T'OD INSULATION F 01 R ROOM 4 INJECTION 0600200 ACCUMULATO LOWHEAD SAFETY 2.38 0.71 RMI 4.3125 0.45 S.S. STD N/A 110" 0 INSULATION F 01 R ROOM 4 INJECTION 0600200 ACCUMULATO LOWHEAD SAFETY 1.05 1.80 RMI 2.475 0.34 S.S. STD N/A 6" OD INSULATION F 01 R ROOM 4 INJECTION 1 0600200 ACCUMULATO LOWHEAD SAFETY 1.05 3.42 RMI 1.975 0.45 S.S. STD N/A 5OD INSULATION F 01 R ROOM 4 INJECTION 0600200 ACCUMULATO LOWHEADSAFETY 1.05 0.84 RMI 4.975 0.55 S.S.: STD N/A 11" OD INSULATION F 01 R ROOM 4 INJECTION N/A ACCUMULATO RESIDUAL HEAT 8.63 51.59 RMI 1.1875 13.11 S.S. STD N/A 11" OD INSULATION G R ROOM 4 REMOVAL I N/A 716'RESIDUAL HEAT 8.63 1.00 MIN-K 0.935 0.20 S.S. STD N/A 10.5" OD INSULATION G R ROOM 4 REMOVAL ACCUMULATO 76 19 REMOVUAL HEAT____________

N/A ACCUMULATO 716' 19 RESIDUAL HEAT 8.63 2.52 RMI 0.6875 0.35 S.S. STD N/A 10" OD INSULATION G R ROOM 4 REMOVAL N/A ACCUMULATO RESIDUAL HEAT 12.75 21.92 RMI 1.125 7.46 S.S. STD N/A 15" OD INSULATION G R ROOM 4 REMOVAL N/A ACCUMULATO RESIDUAL HEAT 12.75 1.50 RMI 2.625 1.32 S.S. STD N/A 18" OD INSULATION G R ROOM 4 REMOVAL N/A 716'RESIDUAL HEAT 1.05 1.75 RMI 2.475 0.33 S.S. STD N/A 6" OD INSULATION G R ROOM 4 REMOVAL N/A ACUUAO 716' 19 RSDAHET 1.05 0.80 RMI 1.475 0.07 S.S. STD N/A 4" OD INSULATION G ACCUMULATO 76 19 REMOVUAL HET5 DINSULATIONG N/A ACUUAO 716' 19 RSDAHET 2.88 0.84- RMI 1.06 0.08 S.S. STID N/A 5"O NUAING R ROOM 4 REMOVAL (TIEBACK SUPPORT) _N/A ACCUMULATO 716' 19 RESIDUAL HEAT 1.05 0.46 RMI 1.975 0.06 S.S. STD N/A 4OD INSULATION G R ROOM 4 REMOVAL NA ACCUMULATO 76 19 REMOVUAL HEAT__6"______NSULATION N/A R716' 19 2.88 0.53 RMI 1.56 0.08 S.S. STD N/A OTINSULRTIG R ROOM 4 REMOVAL (TIEBACK SUPPORT)N/A ACCUMULATO 716' 19 RESIDUAL HEAT 1.05 11.09 RMI 1.475 0.90 S.S. STD N/A 4" OD INSULATION (DRAIN G R ROOM 4 REMOVAL LINE)N/A ACCUMULATO 716' 19 RESIDUAL HEAT 1.05 1.07 RMI 1.975 0014 S.S. STD N/A 5" OD INSULATION (DRAIN G R ROOM 4 REMOVAL VALVE)0 ACCUMULATO RESIDUAL HEAT 716'0 UR A14.00 10.50 RMI 2 7.33 S.S. STD N/A 18" 00 INSULATION H 01 RROOM 4 1 REMOVAL 7.33 _ _ _ I I ALION-CAL-TVA-2739-03 Revision 3 Attachment A 21 of 25 I WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS OD LENGTH INSUL. INSULATION (IN) (FT) TYPE THICKNESS (IN)INSUL. JACKET BUCKLE I STRAP VOLUME .. ... .. ..COMMENTS PACKET LETTER (FT3)MATERIAL PYIE TYPE 10.75 6.00 RMI 2.125 3.58 S.S. STD N/A 15" OD INSULATION H 14.00 3.11 RMI 9.5 15.15 S.S. STD N/A 3300 INSULATION H (VALVE)10.75 2.72 RMI 8.625 9.92 S.S. STD N/A 2800 INSULATION H (VALVE)3.50 0.34 RMI 1.75 0.07 S.S. STD N/A T'OD INSULATION H 1.05 0.82 RMI 0.975 0.04 S.S. STD N/A 3OD INSULATION H 8.63 39.75 RMI 1.1875 10.11 S.S. STO N/A 11" OD INSULATION J 8.63 5.17 MIN-K 0.9375 1.01 S.S. STD N/A 10.5" 00 MIN-K INSULATION 4.50 14.67 RMI 1.75 3.50 S.S. STD N/A 8" OD INSULATION K 4.50 1.17 RMI 4.75 1.12 SS, STD N/A 14" OD INSULATION K 4.50 0.80 RMI 3.75 0.54 S.S. STD N/A 12" OD INSULATION K 1.06 3.80 RMI 1.47 0.31 S.S. STD N/A 4" OD INSULATION K 1.06 1.71 RMI 2.47 0.33 S.S. STD N/A 6" OD INSULATION K 2.38 1.83 RMI 1.31 0.19 S.S. STD N/A 5OD INSULATION K 2.38 0.26 RMI 3.31 0.11 S.S.STD N/A 9" OD INSULATION K MIN-K N/A N/A MIN-K 0.72 0.04 N/A N/A N/A N/A L RETURN/SUPPLY 2L29.03 3 10.22 S.S. N/A STD EL. 756' TO EL. 769'-10 5/8" A LINES SS ETURN/SUPPLY2.38 10.10 3 3.56 N/A N/A N/A EL. 771'-6" A LINES STIC.ETURN/SUPPLY 6.25 FOAMPLA 3 1.57 N/A N/A N/A EL, 771'-6" A LINES 0 STIC ETURN/SUPPLY2.38 14.10 3 4.96 N/A N/A N/A EL. 776-0" A LINES STIC 0ETURN/SUPPLY 8.75 FOAMPLA 3 2.20 N/A N/A N/A EL. 775'-0" A LINES STIC ALION-CAL-TVA-2739-03 Revision 3 Attachment A 22 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM ~INSUL. PCE PROBLEM LOCATION ELEV. AREA DESCRIPTION OD LENGTH INSUL INSULATION VOLU JACKET BUCKLE STRAP PACKET NUMBER (IN) (FT) TYPE THICKNESS (IN) VOLUME COMMENTS (FT3) MATERIAL TYPE TYPE UPPER GLYCOL RETURN/SUPPLY FOAMGLA N/A CONTAINMEN 756' 20 0.84 2.50 3 0.63 S.S. N/A STD CHECK VALVES A TLINES SS UPPER GLYCOL RETURN/SUPPLY SEE FOAMPLA 1 1.65 N/A N/A N/A N/A CONTAINMEN 756' 20 SEE CALC 16AA ATSUPPORTS A T LINES CALC STIC ICE N/A C E 803' 21 VENT-CURTAINS N/A SEE CALC SEE CALC SEE CALC 2.20 N/A N/A N/A N/A A CONDENSER N/A ICE 803'SEAL FRAME & VESSEL N/A SEE CALC SEE CALC SEE CALC 8.38 N/A N/A N/A N/A A CONDENSER SHELL N/A ICE GLYCOL RETURN/SUPPL 2.38 318.00 3 111.97 S.S. N/A STD N/A B CONDENSER LINES SS N/A ICE 756' GLYCOL RETURN/SUPPLY 1.05 264.00 3 69.98 S.S. N/A STD N/A B CONDENSER LINES SS ICE FOAMGLA N/A CONDEN 12.75 255.00 3 262.86 S.S. N/A STD N/A B CONDENSER 76 2 DRILIE 127 25.0 SS__________

ICE 819'-7 TOP DECK BLANKET SEE STITCHE N/A 21 SEE CALC SPONGE 0.75 444.00 S.S. N/A 2 BLANKET LAYERS C CONDENSER 1/2" ASSEMBLY CALC ____S ICE SEE FOAM N/A 803' 21 END WALLS/DOORS SEE CALC 1 40.20 N/A N/A N/A N/A D CONDENSER CALC RUBBER ICE FOAMGLA S.S. JACKETING USED ON N/A 803' 21 GLYCOL SUPPLY LINE 6.63 29.81 18.78 N/A N/A N/A SOME PIPING OUTSIDE E CONDENSER 83SS OF ICE CONDENSER BAY A ICE 1 FOAMGLA S.S. JACKETING USED ON N/A 803' 2 LYCOL SUPPLY LINE 3S 3 7.02 N/A N/A N/A SOME PIPING OUTSIDE E CONDENSER 83 2 GOF ICE CONDENSER BAY ICE FOAMPLA S.S. JACKETING USED ON N/A CONDENSER 803' 21 GLYCOL SUPPLY LINE 4.50 553.47 STIC2.5 211.31 N/A N/A N/A SOME PIPING OUTSIDE E OF ICE CONDENSER BAY S.S. JACKETING USED ON N/A 3CE 803' 21 GLYCOL RETURN LINE 6.63 10.00 OS 6.30 N/A N/A N/A SOME PIPING OUTSIDE E E SS OF ICE CONDENSER BAY ICE FOAMGLA S.S. JACKETING USED ON N/A CONDENSER 803' 21 GLYCOL RETURN LINE 4.50 29.67 14.56 N/A N/A N/A SOME PIPING OUTSIDE E OF ICE CONDENSER BAY ICE FOAMPLA S.S. JACKETING USED ON N/A CONDENSER 803' 21 GLYCOL RETURN LINE 4.50 529.00 STIC2.5 201.97 N/A N/A N/A SOME PIPING OUTSIDE E IE IST IC IOF ICE CONDENSER BAY ICE GLYCOL SUPPLY BY-PASS FOAMPLA 2 1 N 803' 21 0.84 7.17 2.5 1.31 N/A N/A N/A N/A E N/A CONDENSER 8 2 LINE T C I I I I ALION-CAL-TVA-2739-03 Revision 3 Attachment A 23 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM OD LENGTH INSUL. INSULATION JACKET BUCKLE STRAP PACKET NUMBER LOCATION ELEV. AREA DESCRIPTION (IN) (FT) TYPE THICKNESS (IN) VOLUME MATERIAL TYPE TYPE COMMENTS LETTER N/A IE 83 2 GCLSPLYAS08 FOAMGLA_____________

3_______0.1_(F3)

N/A_ _ N/A__N/A__VALVE

__ E N/A ICE 83 21 GLYCOL SUPPLY BY-PASS 0.4 0.50 FOAMGLA 3 0.13 NIA N/A N/A VALVE E CONDENSER LINE SS N/A ICE 803' 21 GLYCOL RETURN BY- 0.84 8.27 FOAMPLA 2.5 1.51 N/A N/A N/A N/A E CONDENSER PASS LINE STIC N/A N/A N/A ICE 803' 21 GLYCOL RETURN BY- 0.84 0.50 FOAMGLA 3 0.13 N/A N/A N/A VALVE E CONDENSER PASS LINE SS N/A ICE 803' 21 GLYCOL EXPANSION 3.50 0.59 FOAMPLA 2.5 0.19 N/A N/A N/A N/A E CONDENSER TANK LINES STIC N/A ICE 803' 21 GLYCOL EXPANSION 1.32 32.72 FOAMPLA 2.5 6.82 N/A N/A N/A N/A E CONDENSER TANK LINES I STIC N/A ICE 803' 21 GLYCOL SUPPLY/RETURN 1.32 750.00 FOAMPLA 2.5 156.26 N/A N/A N/A N/A E CONDENSER LINES TO AHU'S 1 STIC N/A ICE 803' 21 HEADER LINES 1.90 462.55 FOAMGLA 3 148.34 S.S. N/A STD N/A E CONDENSER SS N/A ICE 803' 21 HEADER/AHU 1.90 150.00 FOAMGLA 3 48.11 S.S. N/A STD N/A E CONDENSER DRAINS/TRAPS SS N/A ICE 803' 21 HEADESCAHU 1.90 60.00 FOAMPLA 2.5 14.40 S.S. N/A STD N/A E CONDENSER DRAINS/TRAPS STIC .N/A ICE 803' 21 TOP DECK BEAMS N/A SEE CALC FOAMPLA 1 1376.00 N/A N/A N/A N/A F CONDENSER STIC N/A ICE 803' 21 DUCT FLEX N/A SEE CALC SEE CALC SEE CALC 0.32 N/A N/A N/A N/A G CONDENSER CONNECTIONSIII N/A ICE 803' 21 DUCT FLEX N/A SEE CALC SEE CALC SEE CALC 4.59 N/A N/A N/A N/A G CONDENSER CONNECTIONS N/A ICE 803' 21 VENT-CURTAINS N/A SEE CALC SEE CALC SEE CALC 3.89 N/A N/A N/A N/A H CONDENSER 38 N/A REACTOR 713' 22 REACTOR VESSEL SEE SEE CALC RMI SEE CALC 810.76 S.S. STD N/A N/A A VESSEL CALC_N/A REACTOR 713' 22 REACTOR VESSEL 1.06 SEE CALC RMI 1.47 1.57 S.S. STD N/A FILLED WITH MED. S.S. A VESSEL I WOOL N/A PRESSURIZER 729' 23 PRESSURIZER SEE SEE CALC RMI SEE CALC 449.41 S.S. STD N/A N/A A CALC1 0600200 PRESSURIZER 729' 23 6" PRESSURIZER SPRAY 5.56 0.29 RMI 7.22 0.58 S.S. STD N/A 20" OD INSULATION B 02 LINE 0600200 PRESSURIZER 729' 23 6" PRESSURIZER SPRAY 5.56 0.38 RMI 2.22 0.14 S.S. STD N/A 10" OD INSULATION B 02 LINE 1 0600200 PRESSURIZER 729' 23 6" PRESSURIZER SPRAY 4.50 0.79 RMI 2.75 0.34 S.S. STD N/A 10" OD INSULATION B 02 LINE I 0600200 PRESSURIZER 729' 23 6" PRESSURIZER SPRAY 6.62 49.34 RMI 2.69 26.96 S.S. STD N/A 12" OD INSULATION B 02 LINE 0600200 PRESSURIZER 729' 23 6" PRESSURIZER SPRAY 6.62 0.65 RMI 2 0.24 S.S. STD N/A 8.5" OD INSULATION B 02 LINE 0600200-13-PRESSURIZER 729' 23 6" PRESSURIZER SPRAY 1.05 1.05 RMI 2.975 0.27 S.S. STD N/A T7OD INSULATION B 02 PLINE 0600200 PRESSURIZER 729' 23 3" AUXILIARY SPRAY LINE 3.50 16.75 RMI 2.75 6.28 S.S. STD N/A 9OD INSULATION B 0202 _____ ______________________

_____ _____ _______________

_____________________________________

ALl ON-CAL-TVA-2739-03 Revision 3 Attachment A 24 of 25 WATTS BAR NUCLEAR PLANT UNIT 1 WALK DOWN RESULTS PROBLEM OD LENGTH INSUL. INSULATION VOLUM JACKET BUCKLE STRAP PACKET NUBR LOCATION ELEV. AREA DESCRIPTION (N (F) TP THCES(I)VOLUME MAEIL TP YECOMMENTS LTE NUMBER (IN) (FT) TYPE THICKNESS (IN) (F3 MAEAL TP TYEETR 002 (FT3)0600200 PRESSURIZER 729' 23 3" AUXILIARY SPRAY LINE 3.50 1.34 MIN-K 0.56 0.07 S.S. STD N/A 4.62" OD INSULATION B 02 0600200 02 PRESSURIZER 729' 23 3" AUXILIARY SPRAY LINE 3.50 1.30 RMI 0.75 0.09 S.S. STD N/A 5OD INSULATION B 0600200 02 PRESSURIZER 729' 23 3" AUXILIARY SPRAY LINE 3.50 1.46 RMI 6.25 1.94 S.S. STD N/A 16" OD INSULATION B 0600200 PRESSURIZER 729' 23 3" AUXILIARY SPRAY LINE 3.50 0.70 MIN-K 1.5 0.11 S.S. STD N/A 6.5" OD INSULATION B 02 N/A PRESSURIZER 729' 23 3/4" INSTRUMENTATION 1.05 5.84 RMI 4.98 3.83 S.S. STD N/A 11" OD INSULATION C N/A PRESSURIZER 729' 23 3/4" INSTRUMENTATION 1.05 1.46 RMI 3.98 0.64 S.S. STD N/A 9 OD INSULATION C N/A PRESSURIZER 729' 23 PRESSURE RELIEF 6.63 9.84 RMI 2.6875 5.37 S.S. STD N/A 12" OD INSULATION D N/A PRESSURIZER 729' 23 PRESSURE RELIEF 3.50 2.67 RMI 6.5 3.79 S.S. STD N/A 16.5" OD INSULATION D N/A PRESSURIZER 729' 23 PRESSURE RELIEF 3.50 4.27 RMI 2.75 1.60 S.S. STD N/A 9OD INSULATION D 1600O INSULATION N/A PRESSURIZER 729' 23 PRESSURE RELIEF 12.00 1.11 RMI 2 0.68 S.S. STD N/A 1 FLANGE) D (FLANGE)N/A PRESSURIZER 729' 23 PRESSURE RELIEF 3.50 1.67 RMI 3.75 0.99 S.S. STD N/A 11" OD INSULATION D N/A PRESSURIZER 729' 23 PRESSURE RELIEF 3.50 0.64 RMI 2.25 0.18 S.S. STD N/A 8" OD INSULATION D N/A PRESSURIZER 729' 23 PRESSURE RELIEF 12.00 1.11' RMI 2.25 0.78 S.S. STID N/A 1."OINUAON D (FLANGE) , N/A PRESSURIZER 729' 23 PRESSURE RELIEF 1.06 1.98 RMI 2.97 0.52 S.S. STD N/A 7OD INSULATION D INSTRUMENT 716' 24 LETDOWN LINE 3.50 16.67 RMI 3.25 7.98 S.S. STD N/A N/A A 10 ROOM N/A INSTRUMENT 716' 24 LETDOWN LINE 3.50 30.84 RMI 3.25 14.76 S.S. STD N/A N/A B ROOM N/A INSTRUMENT REGENERATIVE HEAT 10.90 SEE CALC RMI 3.05 45.63 S.S. STD N/A N/A B ROOM EXCHANGER 0600200 INSTRUMENT 716' 24 LETDOWN LINE 3.50 15.34 RMI 1.74 3.05 S.S. STD N/A N/A C 09 ROOM 0600200 INSTRUMENT 716' 24 NORMAL CHARGING LINE 3.50 23.67 RMI 2.75 8.88 S.S. STO N/A AT 900 INSULATION 0 11 ROOM I__ 1___ 1__ _________0600200 INSTRUMENT 716' 24 NORMAL CHARGING LINE 3.50 1.24 RMI 1.25 0.16 S.S. STD N/A AT 6" OD INSULATION D 11 ROOM 0600200 INSTRUMENT 716' 24 NORMAL CHARGING LINE 3.50 2.82 RMI 1.75 0.57 S.S. STD N/A AT6" OD INSULATION D 11 ROOM I 1_1 000200 INSTRUMENT 7ALTERNATE CHARGING 3.50 1.18 RMI 2.75 0.44 S.S. STD N/A AT 9" OD INSULATION D 11 ROOM 7 LINE 0600200 INSTRUMENT ALTERNATE CHARGING 3.50 1.69 RMI 2.25 0.48 S.S. STD N/A AT 8" OD INSULATION D 11 ROOM 7 LINE I ALION-CAL-TVA-2739-03 Revision 3 Attachment A 25 of 25 WATTS BAR NUCLEAR PLANT UNIT I WALK DOWN RESULTS INSUL.PROBLEM OD 'LENGTH INSUL. INSULATION INU. JACKET BUCKLE STRAP PACKET PUOBEM LOCATION ELEV. AREA DESCRIPTION ( ( T INSUTIN VOLUME JACET BUKE TRP COMMENTS PACKET NUMBER (IN) (FT) TYPE THICKNESS (IN) LETTER 0600200 INSTRUMENT 716' 24 NORMAL CHARGING 1.05 3.34 RMI 1.975 0.44 S.S. STD N/A AT 5" OD INSULATION D 11 ROOM BYPASS LINE 0600200 INSTRUMENT NORMAL CHARGING 1.05 1.80 RMI 0.975 0.08 S.S. STD N/A AT 4" OD INSULATION 1)11 Room BYPASS LINE 0600200 INSTRUMENT 716' 24 AUXILIARY SPRAY LINE 2.38 10.84 RMI 2.81 3.45 S.S. STD N/A AT 8" OD INSULATION D 11 ROOM 0600200 INSTRUMENT 716' 24 AUXILIARY SPRAY LINE 3.50 1.05 RMI 2.75 0.39 S.S. STD N/A AT 9" OD INSULATION 0 02 ROOM 0600200 INSTRUMENT 716' 24 AUXILIARY SPRAY LINE 3.50 0.84 RMI 0.25 0.02 SS. STD N/A AT 4" OD INSULATION D 02 ROOM 0600200 INSTRUMENT 716' 24 AUXILIARY SPRAY LINE 3.50 0.59 RMI 0.75 0.04 S.S. STD N/A AT 5" OD INSULATION D 02 ROOM 0600200 INSTRUMENT 716' 24 AUXILIARY SPRAY LINE 3.50 2.21 RMI 0.5 0.10 S.S. N/A STD AT 4.5" OD INSULATION D 02 ROOM N/A INSTRUMENT RESIDUAL HEAT 8.63 55.34 RMI 1.1875 14.07 S.S. STD N/A 11 OD INSULATION E ROOM REMOVAL 0600200 INSTRUMENT LOWHEAD SAFETY 8.63 72.67 RMI 1.1875 18.47 S.S. STD N/A 11" OD INSULATION F 02 ROOM 7 INJECTION_

0600200 INSTRUMENT 716' 24 EXCESS LETDOWN 1.32 16.67 RMI 2.34 3.11 S.S. STD N/A 6" OD INSULATION G 12 ROOM 0600200 INSTRUMENT 716' 24 EXCESS LETDOWN 1.32 1.17 MIN-K 1.34 0.09 S.S. STD N/A 4OD INSULATION G 12 ROOM 0600200 INSTRUMENT 716' 24 EXCESS LETDOWN 1.32 0.72 RMI 1.84 0.09 S.S. STD N/A 5" OD INSULATION G 12 ROOM 0600200.08-INSTRUMENT 716' 24 EXCESS LETDOWN 1.05 0.93 RMI 2.84 0.22 S.S. STD N/A T7OD INSULATION G 12 ROOM N/A INSTRUMENT720-737 24 3M-M2C 1.90 50.00 3M-M20C 0.1875 2.19 N/A N/A N/A SEE CALCULATION H ROOM INSULATION N/A 720-737 24 3M-M2C 0.68 50.00 3M-M20C 0.1875 1.00 N/A N/A N/A SEE CALCULATION H ROOM INSULATION I INSTRUMENT CONDUIT 3M-M20C SUPPORT INSULATION H N/A ROM 720-737 24 INSULT N/A N/A 3M-M20C 0.1875 1.54 N/A N/A N/A SEE CALULATION H ROOM INSULATION ISEE CALCULATION N/A INSTRUMENT 720-737 24 MIN-K INSULATION 0.68 20.00 MIN-K 0.75 1.06 N/A N/A N/A SEE CALCULATION H ROOM N/A INSTRUMENT EXCESS LETDOWN HEAT 18.75 SEE CALC RMI SEE CALC 4.00 S.S. STD N/A 25" OD INSULATION J ROOM EXCHANGER N/A INSTRUMENT 716' 24 EXCESS LETDOWN 1.32 6.00 RMI 2.34 1.12 S.S. STD N/A 6" OD INSULATION K_____ ROOM _________

_______ ____ __ ___________

N/A INSTRUMENT 716' 24 EXCESS LETDOWN 1.32 1.32 RMI 2.84 0.34 S.S. STD N/A 7" OD INSULATION K ROOM I N/A INSTRUMENT 716' 24 EXCESS LETDOWN 1.32 0.84 RMI 4.34 0.45 S.S. STD N/A 10" OD INSULATION K ROOM I I I I Watts Bar Reactor Building GSI-191 Debris Generation Calculation N Document No: ALION-CAL-TVA-2739-03 Rev:3 Page: B-I of B-3 ATTACHMENT B -CARBOZINC T M 11 This Attachment contains the data sheet for CarbozincTM 11 taken off of the Carboline website (http://www.carboline.com/).

ALION-CAL-TVA-2739-03, Rev. 3... .............

..Attachmmnt B _P~aae_2_of

........Carbozinc 11 SG'M 01, p'N 7K o ~Seeto & Specification3Dat Generic Type Self-curing, solvent based, inorganic zinc silicate Description An inorganic zinc rich primer that protects steel galvanically, eliminating sub-film corrosion.

[Sstae & ufc.Pea -0 lo0 General Steel Remove all oil or grease from the surface to be coated with Thinner 2 or Carboline Surface Cleaner 3 (refer to Surface Cleaner 3 instructions) in accordance with SSPC-SP1.Non-Immersion Service: Abrasive blast to a Commercial Finish in accordance with SSPC-SP6 and obtain a 1-3 mil (25-75 micron) blast profile.Features Color Finish Topcoats Dry Film Thickness Solids Content Theoretical Coverage Rate" Excellent corrosion and weathering protection." High zinc loading per square foot." Meets Class "B" slip co-efficient and creep testing criteria for use on faying surfaces." Very good resistance to salting." Meets nuclear requirements for level one areas." Available in an ASTM D520, Type 2 zinc version.Green (0300) and Gray (0700).Matte May be topcoated with epoxies, phenolics, acrylics, silicones, vinyls, chlorinated rubbers or others as recommended.

Do not topcoat with alkyds.2.0 -3.0 mils (50 -75 microns) per coat Don't exceed 6 mils (150 microns) in a single coat. Excessive film thickness over inorganic zincs may increase damage during shipping or erection.By Weight:: 79% + 2%Total zinc in dry film: 85% minimum 1000 mil ft 2 (24.5 m 2/1 at 25 microns)333 ft 2 at 3 mils (8.2 m 2/1 at 75 microns)Allow for loss in mixing and application.

As measured per NACE 6A181. Material losses during mixing and application will vary and must be taken into consideration when estimating job requirements.

Exposure Splash & Spillage Fumes Acids Very Good* Excellent*

Alkalies Very Good* Excellent*

Solvents Excellent Excellent Salt Excellent Excellent Water Excellent Excellent*With suitable topcoat.VOC Values As supplied:

4.01 lbs./gal (481 g/l)Thinned: 7oz/gal w/Thinner

21: 4.15 lbs./gal (499 g/l)5oz/gal w/Thinner

26: 4.15 lbs./gal (499 g/l)These are nominal values and may vary slightly with color.Dry Temp. Continuous:

750°F (399°C)Resistance Non-Continuous:

800oF (427'C)With recommended silicone topcoats: Continuous:

1000°F (538°C)Non-Continuous:

1200°F (649°C)Limitations Exposure to acids or alkalies without a suitable topcoat or for application over rust inhibitors.

April 2003 replaces January 2002 0231 To the best of our knowledge the technical data contained herein is true and accurate on the date of publication and is subject to change without prior notice. User must contact Carboline Company to verity correctness before specifying or ordering.

No guarantee of accuracy is given or implied. We guarantee our products to conform to Carboline quality control. We assume no resgonsibility for coverage, performance or injuries resulting from use. Liability, if any, is limited to replacement of products.

NO OTHER WARRANTY OR GUARANTEE OF ANY KIND IS MADE BY ARBOL NE, EXPRESS OR IMPLUED, STATUTORY, BY OPERATION OF LAW, OR OTHERWISE, INCLUDING MERCHANTABILITY AND FITNESS FOR A PARTICULAR PURPOSE, Carbotine and Carbozinc are registered trademarks of Carboline Company.

ALION-CAL-TVA-2739-03, Rev. 3 Attachment B, Page 3 of 3 Carbozinc

.11 SG Apci E q ui pm Listed below are general equipment guidelines for the application of this product.Job site conditions may require modifications to these guidelines to achieve the desired results.General Guidelines:

Equipment Guidelines (General)The following spray equipment has been found suitable and is available from manufacturers such as Binks, DeVilbiss and Grace. Agitate the mixed material continuously during application.

If spraying stops for more than 10 minutes, recirculate the material remaining in the spray line.Conventional Agitated pressure pot equipped with dual regulators, Spray 3/8" I.D. minimum material hose, 50' maximum material hose .070" I.D. fluid tip and appropriate air cap.Airless Spray Pump Ratio: 30:1 (minimum)*

GPM Output: 3.0 (minimum)Material Hose: 3/8" I.D. (minimum)Tip Size: .019-.023" Output PSI: 1500-2000 Filter Size: 60 mesh'Teflon packings are recommended and available from the pump manufacturer.

Brush For touch up of areas less than one square foot only.Use medium bristle brush. Avoid excessive rebrushing.

Roller Application by roller is not recommended.

Miin & Thnnn Condition Material Surface Ambient Humidity 40-95°F 40°-110°F 40-95°F Normal ( C 40-90%(4--35°C) 14-43°C (4°-_35°C 0°F 0°F 0°F Minimum (-18-C) 18 C 18 30%130°F 200°F 130°F Maximum (3C 5 C 95%(54°C) 93C C54°)This product simply requires the substrate temperature to be above the dew point. Condensation due to substrate temperatures below the dew point can cause flash rusting on prepared steel and interfere with proper adhesion to the substrate.

Special application techniques may be required above or below normal application conditions.

Cuin Schdul Surface Temp. & Immersion 50% Relative Handle Topcoat Service HumiditySevc 0F (-18'C) 4 Hours 7 Days N/R 40°F (4-C) 1 Hour 48 Hours 72 Hours 60°F (16°C) 45 Minutes 24 Hours 48 Hours 80°F (27°C) 45 Minutes 18 Hours 18 Hours 100°F (38°C) 15 Minutes 16 Hours 14 Hours These times are based on a 2-3 mil (50-75 micron) dry film thickness and a 50%Relative Humidity or higher. Higher film thickness, insufficient ventilation or cooler temperatures will require longer cure times and could result in solvent entrapment and premature failure.For shop applications or tank linings, if the relative humidity is low, the curing time can be reduced by raising the Relative Humidity by steam or a water spray on the coated surface after an initial dry time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at 75°F (240C).Notes: 1. Any salting that appears on the zinc surface as a result of prolonged weathering exposure must be removed prior to the application of additional coatings.2. Loose zinc dust must be removed from the cured film by rubbing with fiberglass screen wire if: a. The Carbozinc 11 SG is to be used without a topcoat in immersion service and "zinc pickup" could be detrimental, or b. When overspray is evident on the cured film and a topcoat will be applied."- -' -- 5 S. S *Mixing Ratio CZ 11 SG Base Zinc Filler/Special Zinc Filler Thinning Pot Life Power mix base, then combine and power mix as follows: 1 Gallon Kit 5 Gallon Kit 1 gallon (partially filled) 5 gallon (partially filled)14.6 lbs. 73 lbs.May be thinned up to 5 oz/gal with Thinner #26. In cool weather, below 40°F (40C), may be thinned up to 7 oz/gal with Thinner #21. Use of thinners other than those supplied or recommended by Carboline may adversely affect product performance and will void product warranty whether express or implied.Pot life ends when material becomes too thick to use.Material Temperature Time 60oF (160C) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 75°F (240C) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 90°F (32-C) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Iceaup&Saet Shipping Weight (Approximate)

Flash Point (Setaflash)

Storage Temperature

& Humidity Shelf Life 1 Gallon Kit 23 Lbs. (10 kg)5 Gallon Kit 113 Lbs. (51 kg)Cleanup Safety Ventilation Caution Use Thinner #21 or isopropyl alcohol. In case of spillage, absorb and dispose of in accordance with local applicable regulations.

Read and follow all caution statements on this product data sheet and on the MSDS for this product. Employ normal workmanlike safety precautions.

Hypersensitive persons should wear protective clothing, gloves and use protective cream on face, hands and all exposed areas.When used in enclosed areas, thorough air circulation must be used during and after application until the coating is cured. The ventilation system should be capable of preventing the solvent vapor concentration from reaching the lower explosion limit for the solvents used. User should test and monitor exposure levels to insure all personnel are below guidelines.

If not sure or if not able to monitor levels, use MSHA/NIOSH approved respirator.

This product contains flammable solvents.

Keep away from sparks and open flames. All electrical equipment and installations should be made and grounded in accordance with the National Electric Code. In areas where explosion hazards exist, workmen should be required to use non-ferrous tools and wear conductive and non-sparking shoes.55°F (130C) for Carbozinc 11 SG Base 400 -100°F (40 380C) Store indoors.0-90% Relative Humidity Carbozinc 11 SG Base: 6 Months at 75°F (240C)Zinc Filler/Special Zinc Filler. 24 Months at 75°F (24°C)*Shelf Life: (actual stated shelf life) when kept at recommended storage conditions and in original unopened containers.

Note: The Carbozinc 11SG base is unusable if the material is jelly-like, stringy or does not properly atomize with conventional spray equipment. 350 Hanley Indufrial Ceurt, St Louis, MO 63144-1599 314/644-1000 314/644-4617 (fax) www .carbtltne.mnCospany April 2003 replaces January 2002 To the best of our knowledge the technical data contained herein is true and accurate on the date of publication and is subject to change without prior notice. User must contact Carboline Company to verify correctness before specifying or ordering.

No guarantee of accuracy is given or implied. We guarantee our products to conform to Carboline quality control. We assume no responsibility for coverage, performance or injuries resulting from use. Liability, if any, is limited to replacement of products.

NO OTHER WARRANTY OR GUARANTEE OF ANY KIND IS MADE BY CARBOL/NE, EXPRESS OR IMPLIED, STATUTORY, BY OPERATION OF LAW, OR OTHERWISE, INCLUDING MERCHANTABILITY AND FITNESS FOR A PARTICULAR PURPOSE. Carboline and Carbozinc are registered trademarks of Carboline Company.

Watts Bar Reactor Building GSI-191 Debris Generation Calculation

ýA LA:0 N Document No: ALION-CAL-TVA-2739-03 Rev:3 Page: C-1 of C-3 ATTACHMENT C -CARBOLINE T M 295 This Attachment contains the data sheet for CarbolineTM 295 taken off of the Carboline website.(http://www.carboline.com/).

ALION-CAL-TVA-2739-03, Rev. 3 Attachment C., Page 2 of 3 A EN: Pi PA 1, e D OrP-P ion NC* GENERAL EDE: FORF~iS I~ bP Wna' (Iec ep yI Cioi!Oi 0 "PISTAWCE

.4m etsi~~o u PRECGMWIEN[GED DRY PLMA T HItCKNIYSM7 PERi "Q'AT T1~~RE~C~CCQVEPAL2E P--? MIXED ALC~~l9ý V..S .I V ~21 ti r; ( n~'(C i r~i Q *NOHEL ~,tFFiII7ss0Ur~oaqac.~pip ,Isr A:irOXIMATE SHiPPING WEIGHT Carbitne29b I3 Sfrtser 0 (i I43~I~,5~a.7O4.

FLEXiO&ITY

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Certiolor M~, lAO ~itaoe V.~r B P cas ms b~ jOP'n4d *tro'r Carbotno sates R~ori-~er

~Of A ~ C 1~.1unn~evir cam Up Note PIoa~e ice' to scp2r~,.e rippInUiriQO r a ic P. 5 .0 more '.p n.tin~ daIs r pri p SURFACE PROPARATIONS 4env n )l ree'"n U5T" Pi q~5wt i~ as o~d r li i-.W 'FF.O-...iiS. , .~ -~ .5ii.* -I ALION-CAL-TVA-2739-03, Rev. 3 Attachment C, Page 3 of 3 Carboline:'

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.......i ..: Watts Bar Reactor Building GSI-191 Debris Generation Calculation A L , Vi0O.N Document No: ALION-CAL-TVA-2739-03 Rev:3 Page: D-1 of D-3 ATTACHMENT D -PHENOLINE T M 305 This Attachment contains the data sheet for PhenolineTM 305 faxed to Alion.

I11/ 03,,04 '10 :18 F-AX~ 314 644 6883 CAýTKTNE¶~

Fh n' ýEarboli e PHENOLINE~

305 FINISH SELECTION DATA SPECIFICATION DATA GENERIC TYPE: Moodhied phenollco.

Part' A and B mixed pror to application, GENERAL PROPERTIES:

PHENNOLINE 305 Finlstih Is a Iheavy duty topcoat which sets to a hard, tough, smnooth finis having very good abrasion reigtaiice.

Thea surfaco is glosy and hans excellent resslanc*

to a wida range of solvents, c-ustlcs, cleanlng sotlltorw rnd add entrained vapors' af high concentralion.

Fesalures include: Highly chemiceal re-sistant Vilm* Very cood abrasion resistance

Excellont res.istanvo to hydraulic fluids D utstanding chemical and phy-sical properties

Meeits mocst VOC CVolatlle Organic Contoni) regtiations RECOMMENDED USES: PHENOILINE 305 Finish is an excellent coatlng for the pwotW~ion of steel anid (oncoee sufface*s In nuclear power plants. Alsýo u-sed in chemnical processing plants, and pulp and paper mills for the preatctlan of rslmdural steel and conayi~ta against severa splash, spillage and fue cond~itins.

The addition of 50 meosh silica provtes a non-sled surface, makin an excellent floor coating.THIEORETICAL SOLIDS CONTENT OF MWED MATERIAL;PH-ENOILNE 3305 Fmnih 6%+/-VOLATIL.E ORGANIC CONTENT (VOC):'The following

'ate nomrinal values: As Supplied:

2.4$ b3 a (291 gasltr ThInned: Utilizing Phenollne Thinner or Thminner #33 0-4 Mulffe Phanoflne Thinnar%hnner #333% Fluid ThInned Oz. Gd 25 q2 25 32 Lbr.3.38 342 405'410*lvAny vary slighrly with xcl.RECOMMJENDED DAY FILM THICKNESS PER COAT, 4-6 mils; (100-150 micon.s)THEORETICAL COVERAGE PER MIXED IlT: 128;3 mil sq, 1, (25.6 sq. rn/I at 25 rnicws), 258 sq ft, at '5 ("its (5.1 sN. Mn/ al 125 microns)6,5 all~onKt, 6416 mn sq. ftý (25,0 sq. ml/ at '25 mic~rors)1285 sq, t. at 5 rnmis (5.1 sN. MAI at 125 nictoS)Mixingq and application liaswill vary~ and must be takenl into consideration when eslimaflng jab reqidrements.

NOT RECOMMENAED FOH: Immersion service spillage of hot or concentrated acids, TYPICAL CHEMICAL RESISTAN.CE.

or continuou:

Acpds'Alka~lies Sclvents Salt Waleor.Splash &Very Good Excellent Excegllent Exceallent STORAGE CONDITIONS:

Sim0 Indoors Temperature:

45-110IPF Humidity:

0-100 SHELF LIFE: 24 monihs when stored at 75'F (24ec)Excellent Exoelent Excredlent Excejllnt Carboinse Repre~senative or Qarlbolirwe Cucmomr Sevis tor GLOSS; High gloss TEMPERATURE RESISTANCE: (Non-immetsion)

Continuous:

2WF (9$cM)Non-rontinuous:

25WF (121'C)~SUaSTRATES:

Apply aver properly primied meaul or cementrlious surfaces.

Surfacer may be requilred for concrete surfaces, deipend-ing9 on roughiness and texture.COMPATIBLE COATINGS; May be applWe over inorganic:

zinca, catalyzodl epoxies, modified phonclics or others as recmommned.

A mist coat may be required when applied over Inorganlc zincs.A topcoat is normally nol reqirod, ConFOl Cai~tuoll Technical SeMRie for SPe'ciflc recommendlations ORDERING INFORMATION Price-, may~ be obtained from yo~rcataCebow Sales Representlative or Ca~ban~e Cusomer Servic Department.

APPROXIMATE .SHIPPING.

WEIGHT: 1.25 Gal. :l: PHENOLINE 3U6 17 Mb. '(7.7 k9)Finish PHENOLINE 9 lbs. (4.1 kg)Thinner (in ones)Thinneor #33 9 lbs. (4.1 kg)(in ones5)FLASH POINT:.$lfl~

PHENOLINE 3a5 Prdmer Parl A PHENUNE 305 Primer Pant a PHENOLINE ThIlnnr Thinner #331_&B0 lb*s(3.3 kq)45 lbs. (20.4 k~g)(in f kves)45 lbs 20A k)'

TIV65)i 63ý1` (1-,;52ýF (l11T)74SF (2n 0)al: (32~C Jan ý1 Replaces March 84 Th N~ b-at 0i ow 4towe. N t' td~ae -t- cWidhegg ý-a W.1d -04 gtt at la iae dt: of i" M d A~ to tiW~t Vý'nue por "m .V =81 mcal~Ia owba toaMP ~W AH ~ ~ g KN YCARSOLUNE EYmS nf gUEQ 5TWTRMB O~ATKIN OF LAW.' Oft O IIEWEBX~tNG~WT~i AND0 FnI555 FO A PRUM"RA PUPPF-5 ALlON-CAL-IVA-2739-03, Rev. 3 Attachment D, Page 2 of 3 11:' 03/0 kTIQN 305 Tlse ^ zouenuo we noc knended Mn iýow PNr imuJuts wid a pfl 1p~ie~rote.

tj I&obult) tJis nizadmvm "k41 ' frcin tJh. nmu&-t SURFACE PREPARATION:

RemOVG ufa 10 be coated With de~an raga Toluol in accordance with SSPC-SP1.rom th E~JO6 I gaifon can 5 qudonca K05 1 qurtr can 1,25 gallon can The following incudion and appeaan4A.

limes aire required to A or approved by C~arboline nmand VOWd prodac warrarey, WnejorW expfo& or Imp1teu.POT LIFE., One and one M hi ours at Nhqhr itemperaiures, Poi jla Ffed eirtf ien begins to sag, APPLICATION TEMPERATURES:

75'F (24'C) and lkss at W~iairi bses body "And (Materlal Surfacep Normal 65-851F 66585'F anvve iefafiori of~t ua. Ott Pass later.The following spray oqriprne avaiablo from manuat~aurm Conventional; Preemwuni pot G mlr~mum material hoseo, .070**2 or xytol.-03, Rev. 3 of 3

iip:ý :Watts Bar Reactor Building GSI-191 Debris Generation Calculation

I:ON Document No: ALION-CAL-TVA-2739-03 Rev:3 Page: E-1 of E-3 ATTACHMENT E -CARBOLINE T M 4674 This Attachment contains the data sheet for CarbolineTM 4674 taken off of the Carboline website.(http://www.carboline.com!).

ALION-CAL-TVA-2739-03, Rev. 3 Attachment E,-Page 2 of:3 C rboine [4674..GENERIC- TVPF, Lcd I a .ori~m: torneeatore..cOstr9 that conino YS0i:e 4-399U [....................." a. U/c: salts -at- ea"]ts t:hanf .200.F97}t~eal etatntnss steet-,Xfro.Is!4 VOC.. :Otpgrart*

Content);9:

4ttgui'obns

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.Thinner (I'-'-.>-4:7.543:10MM HUED 0FRY FILM.ThIJC.NE.PER COAT: THEORiETICAL-COVEU"AGE PEP MIE -ALLON C'tDý ni Ir ,kTl r,- *ant'a, or D&ii et ,- ' ' N i- 1:.4 :.-. a. 4 "osse's::

during' :tait'QK~a:.ir,, :Sn -.d a pirsitor ~,"i.Win.

vary: anti.r riinust:::be, ::ta}ke ::into;:. " hl~Yi esn,5.i- ::ic.:: te~heaaaerrhrteH..

....NOT RECOMMENDED FOR,. as CHdEMICAL GUtD d 5 .iitjtin.g ot .;niroaia.tqn:

ti~kC;c: of aoidsQ or.'-it obsure Adds Alt' dIt'45'41y( 115 S-u....>S-lasitx &::Spiiage 40d ...f cr .RntCs Ct-on 1.0cc.~ooa*V~t y ~oor I er a lent STOR3GE CONDITIOS, Store rncoors..errparattaa<.i-iC-rnidily pi tookn'US uS..TE F'oary75 aaro" .al a 350 -d1Or TOPCOAT EUIE :4ct'a COMPATIBLE

COATI'NGS.:

May acnttac(ve crf tnr'>gi'nn aeo;Vrxin over! -no' Qry- ac S z i tintn ai. t5, -ian .<SEFLF: ..ET.na.tbs:

ins&&.irid...

... t.(24t::COLORS.::

Blatf*:;i.(CSD0O) "ont:: FINISH .Fiat'Pr.e.....

......ti i t t i d -rd. C.........

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ah)o -, C...... i t.. : .nne.. * .10 braS xzkg)ties' 04.444-ir-cwar-t-v

'444 4. .4444. .4 4'.',, par' .44~t4 '4~fltA St"'e nerP42t4ta~nla-0' .44> ~ 444 j4.a. ...41>., i t t .3 .444 4 ,$-t-',-~4-.aa4-y.

...~4,..,t444.,4,.44

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ALION-CAL-TVA-2739-03, Rev.. 3 Attachment E, Page 3 of 3 Catbatin&he-46674 S S Sj~~tAOEc~RLPAftA.liON R3/4-no'-e '4 'at ""'Gao ?'4dn tar a. ~eca '~ aiecs war lnr~"' C ~ ~%~-5~11~ " e lAlana' 3 rae I Si i,~e Qeare; S ~ .,~ ~oteel AIo, q~-~ *ororor y ~. rev ~ec~'arnenaoo nrners 10 e11I041'OO 0 &1P414000 ect ,t e" ~i is to~$4 " *-'" '~P 0' 410> ooie.n a 1 'tar. WA o dti p.o,.Ml~0FG ~. .c~a'G... A '0 ini"'t'tWGflaA'GrC.y Ce Cl" Il'II'sfl'i"HI NNO tiy e tmnrvd AC lci 15 0S'501 (iOr4,, .vijO'a'1111. 4 4 1... ,.'1 4'5' G."d "' A44XcrrlltI tj'J.an trw. ,atrs~'v Mawr nr'.a .1 I3/4Thr "so and t-cd""t wot'aflW.

wiwiner flA4AA~' y Arless"tarp 'Aac (;1A9t"- :p..itlS~"t IA ~~. cs.'f Foe 3. * .11; 1 Ih (. a ', '4'>am .flt,'A A":,:-.. ::oaN:-- t z:: :.. .....:.::... .:.* ' s.i~ .orn kii r' .tt iti ..... ~ .. ........q,. ..* D. l jt(4 r ,n-a-.. -t r. p an- *o y .... ..... .......- .'. .AP~JCATION TEtVIPERATLIR"S NA tonal"1 .... 55 4.tntnn

.rta Il tO ~ta ( ~'i ujHK Sat aeon StY , ft. NSf IS"' "n'1.5 0<'-NWta0 VII Ol Coi flent "-" 52 .Stsdaisn

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tC .. .: : 0'. C l .. 4n ... .. -..y. ... .*: ..:. k ; ' it , ; ~ l ie ; x .; t-: a. In -% :. 5 <.; .! -'go ,.i".. ... ...... .-ittl " ;at; 3/4Tsm i' 7('Y l ' >, .-"'< ". ... E3',,,'," * "i;.. "' ,"' Zst' :].:t151$

Is8C..I cured agrid ,t]? C' i y-'- .. .. ...~CPUTAON 1:READ:A4D OL'.O AL, ACTICN A0SATEMENTS O 'A.dS PRODUCT DATA SHEET AND ON THE> MAERQtA: SAFEY DMIA SHEET FOR ~ ic .Iti PRDUT. 1.... ..-. .-.. ......... ..C-~9'1' ...... t~t.i~CAC E i1 A O ; 's r: 0-0AI§.1 O~. IPIA,1 &k'.ZI I Watts Bar Reactor Building GSI-191 Debris Generation Calculation Document No: ALION-CAL-TVA-2739-03 Rev:3 Page: F-I of F-40 ATTACHMENT F -3M-M20C (INTERAM)This Attachment contains the information, including the data sheet, for 3M-M20C (Interam)insulation as provided by Watts Bar and letter of intent stating how to treat the constituents of 3M-M20C (Interam).

ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 2 of 40 May 18, 2006 Westinghouse Electric Corporation Tft 06042:8 Post Office Box 355 Pittsburgh, PA 15230 Attention:

Krish M. Rajan WATTS BAR NUCLEAR PLANT (WBN)NUCLEAR STEAM SUPPLY SYSTEMS (NSSS)CONTRACT-00026863 LETTER NUMBER W-7929

Subject:

WATTS BAR NUCLEAR PLANT UNIT 1 -CONTRACT WORK AUTHORIZATION NO. WESTINGHOUSE-WBN-2005-008-GSI 191 -CONTAINMENT BUILDING SUMP MULTIDIMENSIONAL FLOW MODEL, NRC GENERIC SAFETY ISSUE GSI-191, "ASSESSMENT OF DEBRIS ACCUMULATION ON PWR SUMP PERFORMANCE" 1. Revision 1 of ALION-CAL-TVA-2739-03, Watts Bar Reactor Building GSI-191 Debris Generation Calculation, contains an assumption for 3M-M20C insulation that concluded the 3M-M20C was to be treated as High Density Fiberglass (HDFG) with a debris size distribution of 100 percent individual fibers. As stated in ALION-CAL-TVA-2739-03, the HDFG fines debris has been shown to be very similar to the Low Density Fiberglass (LDFG) fines debris and therefore the terms are used interchangeably.

Since the issuance of revision 1, the Material Safety Data Sheet (MSDS) for InteramTM M-20A and M-20 and M-20C mat has been obtained (Enclosure 1).The MSDS for 3M-M20C shows that the composition of the insulation is made up of 40-60% vermiculite, 10-15% aluminum silicate, 5-10%organic binder, 5-10% metal foil, with the remaining 5-40% not being specified.

Vermiculite and the metal foil are not fibrous materials and are treated as particulates.

Using a conservative approach, the particulate components are minimized resulting in 45% of the 3M-M20C treated as particulates.

The organic binder, aluminum silicate, and unknown material are assumed to be fibrous resulting in a maximum of 55% fibrous component of 3M-M20C. In addition, since the majority of the 3M-M20C is vermiculite, the density of the expanded 3M-M20C insulation for the particulate component is assumed to be the minimum expanded bulk density of vermiculite, ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 3 of 40 4 lb/cubic feet with a manufactured density of 156 lb/cubic feet (Enclosure 2). The particulate component of 3M-M20C can be conservatively assumed to fail as 10 micron particulate.

2. The bypass fractions for fibrous and particulate insulation are a maximum of 2.42% and 62% respectively (Enclosure 3). This input is being provided for use in the "Downstream Effects Calculations", CN-CSA-05-14 (Debris Ingestion) and CN-CSA-05-36 (Fuel Evaluation).

3. The Downstream Effects Debris Fuel Evaluation, CN-CSA-05-36, also assumes that the bottom fuel nozzles capture 95% of the available fibrous debris. However, based on the analysis of the sample of debris taken in the strainer test flume (sample 1 A), the longest fiber is 3.8 mm or 0.1496 inches (Enclosure 4), which is shorter than the limiting hole size for one third of the fuel (bottom nozzles with alternate p-grid design Cycle 8 core load) but longer than the limiting hole size for the remaining two thirds of the fuel. The remaining two thirds of the fuel will incorporate the alternate p-grid design during the Unit 1 Cycle 8 (Cycle 9 core load) Refueling Outage and Unit I Cycle 9 Refueling Outage (Cycle 10 core load).Thus, cases should be performed to show the results of the fuel evaluation using the bypass fraction above with the additional assumption that a.) 67% of the available fibrous debris is captured on the bottom fuel nozzle and the nozzle on top of the fuel to represent the results after the Unit 1 Cycle 7 refueling outage and b.) 33% of available fibrous debris is captured on the bottom fuel nozzle and the nozzle on top of the fuel to represent the results after the Unit 1 Cycle 8 refueling outage.Questions may be directed to F.A. Koontz at x1261.Sincerely, 1-J. M. Frisco, Jr.Site Engineering Manager EQB 2A-WBN Enclosures cc: M. Gillman BR 3F-C D. M. Lafever, OPS 3C-SQN F. A. Koontz Jr., EQB 2A-WBN L. L. McCormick, EQB 2N-WBN K. A. Lovell, EQB 2N-WBN R. H. Bryan, Jr., LP 4J-C ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 4 of 40 J. S. Robertson, EQB 2N-WBN C. R. Allen, EQB 2N-WBN C. M. Ledbetter, EQB 2N-WBN EDMS, WT CA-K ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 5 of 40 MATERIAL SAFETY 3M DATA SHEET 3M Center St. Paul, Minnesota 55144-1000 1-800-364-3577 or (651) 737-6501 (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )Copyright, 1999, Minnesota Mining and Manufacturing Company.All rights reserved.

Copying and/or downloading of this information for the purpose of properly utilizing 3M products is allowed provided that: 1) the information is copied in full with no changes unless prior agreement is obtained from 3M, and 2) neither the copy nor the original is resold or otherwise distributed with the intention of earning a profit thereon.DIVISION:

SPECIFIED CONSTRUCTION PRODUCTS TRADE NAME: INTERAM(tm)

M-20A AND M-20 AND M-20C MAT ID NUMBER/U.P.C.:

80-6101-1874-9

--80-6101-2301-2 00-51115-02061-2 98-0400-0171-5

--98-0400-0254-9 0400-0255-6 00-51115-02438-2 98-0400-2676-1 00-51115-07590-2 ISSUED: April 12, 1999 SUPERSEDES:

September 08, 1998 DOCUMENT:

10-8339-3.............................................................................

1. INGREDIENT C.A.S. NO. PERCENT VERMICULITE

................................

1318-00-9 40.0 -60.0 ALUMINUM SILICATE .......................

1327-36-2 10.0 -15.0 ORGANIC BINDER .............................

None 5.0 -10.0 METAL FOIL LAMINATE .......................

None 5.0 -10.0 2. PHYSICAL DATA BOILING POINT: ..................

N/A VAPOR PRESSURE:

................

N/A VAPOR DENSITY: .................

N/A EVAPORATION RATE: ..............

N/A SOLUBILITY IN WATER: ...........

INSOLUBLE SPECIFIC GRAVITY: ..............

0.625 PERCENT VOLATILE:

..............

N/A pH:*.............................

N/A VISCOSITY:

......................

N/A MELTING POINT: ..................

N/D APPEARANCE AND ODOR: ODORLESS, GRAY MAT ALUM FOIL OR STAINLESS STEEL ON ONE SIDE Abbreviations:

N/D -Not Determined N/A -Not Applicable CA -Approximately ALION-CAL-TVA-2739-03, Rev. 3 Aftachment F, Page 6 of 40 MSDS: INTERAM(tm)

M-20A AND M-20 AND M-20C MAT April 12, 1999 PAGE 2 3. FIRE AND EXPLOSION HAZARD DATA FLASH POINT: ....................

N/A FLAMMABLE LIMITS -LEL: ........ N/A FLAMMABLE LIMITS -UEL: ........ N/A AUTOIGNITION TEMPERATURE:

...... N/D EXTINGUISHING MEDIA: Non-combustible.

Choose material suitable for surrounding fire.SPECIAL FIRE FIGHT:NG PROCEDURES:

Wear full protective clothing, including helmet, self-contained, positive pressure or pressure demand breathing apparatus, bunker coat and pants, bands around arms, waist and legs, face mask, and protective covering for exposed areas of the head.UNUSUAL FIRE AND.EXPLOSION HAZARDS: Not applicable.

NFPA HAZARD CODES: HEALTH; 0 FIRE: I REACTIVITY:

0 UNUSUAL REACTION HAZARD: none 4. REACTIVITY DATA.............................................................................

STABILITY:

Stable INCOMPATIBILITY

-MATERIALS/CONDITIONS TO AVOID: None HAZARDOUS POLYMERIZATION:

Hazardous polymerization will not occur.HAZARDOUS DECOMPOSITION PRODUCTS: Carbon Monoxide and Carbon Dioxide..............................................................................

5. ENVIRONMENTAL INFORMATION SPILL RESPONSE: Ventilate.

Observe precautions from other sections.

Use toxic dust mask if dust from fired (intensely heated) product is present.Collect spilled material.

If waste dusts, place in a closed container.

RECOMMENDED DISPOSAL: Reclaim if feasible.

Dispose of unfired scrap in a sanitary landfill.Since regulations vary, consult applicable regulations or authorities before disposal of fired scrap. U.S. EPA Hazardous Waste No.: None.Abbreviations:

N/D -Not Determined N/A -Not Applicable CA -Approximately ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 7 of 40 MSDS: INTERAM(tm)

M-20A AND M-20 AND M-20C MAT April 12, 1999 PAGE 3 5. ENVIRONMENTAL INFORMATION (continued)

ENVIRONMENTAL DATA: Not determined.

REGULATORY INFORMATION:

Volatile Organic Compounds:

NID.VOC Less H2C & Exempt Solvents:

N/D.EPCRA HAZARD CLASS: FIRE HAZARD: No PRESSURE:

No REACTIVITY:

No ACUTE: Yes CHRONIC: Yes 6. SUGGESTED FIRST AID EYE CONTACT: None normally required.SKIN CONTACT: None normally required.INHALATION:

None normally required.IF SWALLOWED:

None normally required.OTHER FIRST AID INFORMATION:

None normally required.7. PRECAUTICNARY INFORMATION EYE PROTECTION:

Wear safety glasses with side shields.SKIN PROTECTION:

Avoid prolonged or repeated skin contact.RECOMMENDED VENTILATION:

Provide sufficient ventilation to maintain emissions below recommended exposure limits.RESPIRATORY PROTECTION:

(Avoid breathing of dust created by cutting, sanding or grinding.

Not applicable.

.............................................................................

Abbreviations:

NiD -Not Determined N/A -Not Applicable CA -Approximately E a 0- ic"E E'- I ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 8 of 40 pg C/VP 4, MSDS: INTERAM(tm)

M-20A AND M-20 AND M-20C MAT April 12, 1999 PAGE 4 7. PRECAUTIONARY INFORMATION (continued)

PREVENTION OF ACCIDENTAL INGESTION:

Wash hands after handling and before eating.RECOMMENDED STORAGE: Store under normal warehouse conditions.

FIRE AND EXPLOSION AVOIDANCE; Not applicable.

OTHER PRECAUTIONARY INFORMATION:

Avoid eye contact. Avoid prolonged or frequent skin contact. Gloves or barrier creams may be useful if significant handling is necessary.

Avoid breathing dust and fibers released during processing.

Provide ventilation sufficient to keep dust and fiber concentrations below recommended exposure limits. If concentrations exceed recommended exposure limits, wear a NIOSH-approved dust respirator.+

+NOTE: One manufacturer of ceramic fibers has recommended the use of respirators, regardless of fiber exposure levels.EXPOSURE LIMITS INGREDIENT VALUE UNIT TYPE AUTH SKIN*VERMICULITE

.............................

NONE NONE NONE NONE ALUMINUM SILICATE .......................

1.0 FIBER/CC TWA OSHA ALUMINUM SILICATE ....................

ORGANIC BINDER .......................

METAL FOIL LAMINATE ..................

PROPOSED 1.0 FIBER/CC NONE NONE NONE NONE TWA NONE NONE CMNG NONE NONE* SKIN NOTATION:

Listed substances indicated with 'Y' under SKIN refer to the potential contribution to the overall exposure by the cutaneous route including mucous membrane and eye, either by airborne or, more particularly, by direct contact with the substance.

Vehicles can alter skin absorption.

SOURCE OF EXPOSURE LIMIT DATA:-CMRG: Chemical Manufacturer Recommended Exposure Guidelines

-OSHA: Occupational Safety and Health Administration

-NONE: None Established Abbreviations:

N/D -Not Determined N/A -Not Applicable CA -Approximately 4

ALION-CAL-TVA-2739-03, Rev. 3'f " "vt. Attachment F, Page 9 of 40 MSDS: INTERAM(tm)

M-20A AND M-20 AND M-20C MAT April 12, 1999 PAGE 5.............................................................................

8. HEALTH HAZARD DATA EYE CONTACT: See below SKIN CONTACT: EYE AND SKIN CONTACT: Fibers released during processing may cause mild irritation.

Symptoms may include itching, redness and swelling.Based on 3M studies, normal processing and handling of this product should not result in significant irritation.

INHALATION:

This product contains ceramic fibers and vermiculite bound together with an organic binder. Fibers and dust released during processing may cause mild, transient respiratory irritation.

Symptoms may include cough and itching of the nose and throat.Certain types of ceramic fibers have caused pulmonary fibrosis and cancer in laboratory animals (IARC-2B)

.However, because the fibers are bound in an organic substance, they are not likely to be inhaled during normal handling of the product in this form. Based on 3M studies, normal processing and handling of this product should not result in exposures exceeding the 3M exposure guideline for ceramic fibers. This guideline is based upon the OSHA PEL for asbestos and, thus, is believed to provide an adequate margin of safety for exposures to ceramic fibers. Total fiber concentrations in 3M operations involving cutting this product are Less than 0.1 fibers per cc of air.IF SWALLOWED:

Not determined SECTION CHANGE DATES INGREDIENTS SECTION CHANGED SINCE September 08, 1998 ISSUE REACTIVITY DATA SECTION CHANGED SINCE September 08, 1998 ISSUE Abbreviations:

N/D -Not Determined N/A -Not Applicable CA -Approximately ALION-CAL-TVA-2739-03, Rev. 3 I1CIC&U rC. Attachment F, Page 10 of 40 MSDS: INTERAM(tm)

M-20A AND M-20 AND M-20C MAT April 12, 1999 PAGE 6 The information in this Material Safety Data Sheet (MSDS) is believed to be correct as of the date issued. 3M MAKES NO WARRANTIES, EXPRESSED OR IMPLIED, INCLUDING, BUT NOT LIMITED TO, ANY IMPLIED WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE OR COURSE OF PERFORMANCE OR USAGE OF TRADE. User is responsible for determining whether the 3M product is fit for a particular purpose and suitable for user's method of use or application.

Given the variety of factors that can affect the use and application of a 3M product, some of which are uniquely within the user's knowledge and control, it is essential that the user evaluate the 3M product to determine whether it is fit for a particular purpose and suitable for user's method of use or application.

3M provides information in electronic form as a service to its customers.

Due to the remote possibility that electronic transfer may have resulted in errors, omissions or alterations in this information, 3M makes no representations as to its completeness or accuracy.

In addition, information obtained from a database may not be as current as the information in the MSDS available directly from 3M.

6 ilekar( a~/W / V'(The Container Tree Nursery Manual Volume Two Coniainers and Growing Media Chapter 2 Growing Media Thorn 0-. L jintii-., W'VLi.in NuI,* v .rx'LUiOl, LUSUA rores er .", slatt." ano Primal,. Fu~ru~sliv.

Vorlad,wd t--lk Laidis, -.D. 1990- COodainer%

iiinl l(Jwi l)+ ne'Jifi. \'ii.2. The Conlainer Trt. NuL'iv Mmiual. Agriý .Handihk.F67.1 r Vae higlod. DC-. LI S4. luplirtnv., il , gr .\ tru, Foru.st Service- ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 11 of 40 O~tc~~41 ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 12 of 40 PS. cf 7 Table 2.2.12_. Fhsia c/av'adsri.cs o1t-iriu 4i wtrrkoulhle Konc ci~ri ~ Aer. lion BuIlk deoýý-Iv LU. Illicle sizf"'> porcosity, .atr'r retention Grad Ik, 1 "'i r, weight) 1% volumrc S-4. I.--1 1 2.1 2/8 1 i 1`8- (.6 44.3 297 30.7 24,l .-1 T4.2 .. 01(',-4.7 40.4 412 39.0 3. 60-). I -144.2 1) I00 (),1-2.4 29.9 .30 52.4 4 9(. I-I 7h.2 1f 100 0.1-1. 245 41)0 54.4 S $La " (t-, i. I h .rl ir, ÷-.Figure 2.2.12 ., , "tar I' thl rel-eIs waf.ier, ptr'rif." C. drt'r; 0

!' o , -_ ,,Cra tin a pr ,., .andl drirlage..

According to the Container Nursery Survey, perlite is a minor component of growing media in forest tree nurseries, usually constituting from 10 to 30% of the mix. Perlite is usually added to organic components, such as peat moss, to increase aeration porosity, which is particularly important in the smaller volume containers used in container tree nurseries.

Perlite grades are not standardized, but grades 6, 8, or "propagation grade" are normally used in growing media (table 2.2.13). Perlite grades are also not uniform and contain a range of particle sizes, depending on the sieve sizes used during manufacturing.

Table 2.2.13 -lwiiI -(.ni p, 4r.Ni,_,'f ant horiir. tfltrual cfI.r thh Avvra ge I-lenrwnt cofrpu.iliofl

"/.I 4 7.5.Alurrliuui 7.2 Pi ilasrru, 3u ".5 Sixlit-m VLIA Cahoium 0.6 Magnerniurn( 0.2 Trace O'*eowwi 0.2 BLoutrd wmcv r 1.0 Tý)Io1 .10.0 Av,,-ra~e,'.,' Ipari-lc size Caemlercial la'ling rinirriý\0, e L 3.. I Iorli~cjllural

(.radle--o.eoi,"\o. i 1.70 Horlicultural grade--iine Pri~pa.gal io 3120 Piropa.ation grade 1'T, iere .ore .no .t.lLlrjit p.loliite grcld.., so "each ilal.ll.'WIh lurer li,-n- 1 , tl I iairi g l sal ni..ý'frL'v_ It l'tIt( " e ( .7?M.Perlite has a couple of operational drawbacks.

Horticultural grades of perlite can contain considerable amounts (4% by weight) of very fine particle sizes (Maronek and others 1986) that cause eye and lung Irritation during mixing if the perlite is not pre-moistened.

Because of its closed-cell structure, perlite has a tendency to float to 65 ALION-CAL-TVA-2739-03 Rev. 3 VER1\9CULITE MATERIAL SAFETY DATA SHEET--- SCHU-NDLER COMPAWhment FP]L 1eW4 MATERIAL SAFETY DATA SHEET ---VERMICULITE

-. PRODUCT IDENTIFICATION------

TRADE NAME (as labeled)MANUFACTURERS NAME Address (complete mailing address): Phone number: Date Prepared or Revised: Schundler Company Vermiculite (Expanded)

THE SCHUNDLER COMPANY www.schundler.com 150 Whitman Avenue Edison, N.J. 08817 (732) 287-2244 info@schundler.com February 25, 2004-----------

B.HAZARDOUS INGREDIENTS-------

Chemical Names CAS Numbers Exposure Limits in Air ACGIH TLV (total)ACGIH TLV OTHER)(respirable) 3 mg/M 3 30 mppcf Vermiculite 1318-00-9 10 mg/M3 Vermiculite is the mineralogical name given to hydrated laminar mangesium-aluminum-iron silicates which resemble mica in appearance.

When subjected to heat, crude vermiculite has the unusual property of exfoliating or expanded into worm-like particles (the name vermiculite is derived from the Latin 'vermiculare', meaning to breed worms.)Vermiculite is considered a nuisance dust (also called "Particulates Not Otherwise Classified (PNOC) by ACGIH).Alpha-Cristobalite

& Tridymite:

Less than 0.1%0.01 to 0.05%Alpha Quartz:-------------

II.PHYSICAL PROPERTIES~----

Vapor Density (air = 1)N/A Melting point or range. Co 1350+(Collapse and coalescence of the individual flakes begin at this temperature.)

http://www schundler.com/msdsverm.htm 05/18/2006 ALION-CAL-TVA-2739-03, Rev. 3 VERMICULITE MATERIAL SAFETY DATA SHEET--- SCIHtNDLER COMPM~hment FR- arf46 F~t10L'_.C R e f 0ýSpecific Gravity 2.5 Boiling point or range. F° N/A Solubility in Water <1% Evaporation rate (butyl acetate = 1) N/A Vapor Pressure, mmHg at 200 N/A C Appearance and odor: tan/brown with no odor HOW TO DETECT THIS SUBSTANCE (warning properties of substance as a gas, vapor, dust or mist)Visual only (dust), No gas, vapors, or mist emitted.------------

IV. FIRE AND EXPLOSION~

Flash Point, F° (give method)Auto ignition temperature, F 0 Flammable limits in air, Volume%: Vermiculite is a fully oxidized non-flammable mineral.It is noncombustible and non-flammable.

N/A N/A lower N/A (LEL)upper(UEL)

N/A Fire extinguishing materials:

N/A water spray carbon dioxide__foam dry chemical Special fire fighting procedures:

N/A Unusual fire and explosion NIA hazards: other:-------------------

V. HEALTH HAZARD INFORMATION------------------

SYMPTOMS OF OVEREXPOSURE for each potential route of exposure Inhaled: Contact with skin or eyes: Absorbed through skin: Swallowed:

Coughing Possible eye irritation from dust particles; wear eye protection N/A N/A HEALTH EFFECTS OR RISKS FROM EXPOSURE.http://www.schundler.com/msdsverrnhtm 05/18/2006 ALION-CAL-TVA-2739-03 Rev. 3 VERMICULITE MATERIAL SAFETY DATA SHEET --- SCHUNDLER COMPTAN.hment FP40e t o46 C1Epdii-josL D-? S01 O{ 1 'Acute: Chronic: Target Organ: None Excessive inhalation over long period may cause harmful irritation; use mask suitable for nuisance dust.None FIRST AID: EMERGENCY PROCEDURES Eye Contact: Skin Contact: Inhaled: Swallowed:

Attempt to wash out with clear water; if unable have particle removed by doctor None Remove affected individual from dusty area to area with clean air None SUSPECTED CANCER AGENT?X NO: This product's ingredients are not found in the lists below.YES: Federal OSHA NTP_ IARC MEDICAL CONDITIONS AGGRAVATED BY EXPOSURE Any Respiratory illnesses which a nuisance dust may aggravate-------------

VI. REACTIVITY DATA-Stability:

X Stable Unstable Incompatibility (Materials to avoid): None Hazardous decomposition products (including combustion products):

None Hazardous Polymerization:

__ May Occur X Will not occur Conditions to Avoid: None--------------------

VII. SPILL, LEAK, AND DISPOSAL PROCEDURES-----------

Spill response procedures (include employee protection measures):

Vacuum clean or sweep material; Use respirators suitable for nuisance dust and eye protection.

http://www.schundler.com/msdsverm.htm 05/18/2006 ALION-CAL-TVA-2739-03, Rev. 3 VERMICULITE MATERIAL SAFETY DATA SHEET--- SCHUNDLER COMPA~yhment F1kw t3of45 Preparing wastes for disposal (container types, neutralization, etc.): Dispose in bulk or containers according to local dump requirements.

No special treatment required.Note: Dispose of all wastes in accordance with federal, state, and local regulations.

VIII. SPECIAL HANDLING INFORMATION--

Ventilation and engineering controls: Maintain dust level below TLV.Respiratory protection (type)Masks suitable for nuisance dust.Eye Protection (type)Protective goggles.Gloves (specify material)Not required.Other Clothing and equipment Not required.Work practices, hygienic practices Use good housekeeping to avoid transient dust.Other handling and storage requirements Use good housekeeping to avoid transient dust.Protective measures during maintenance of contaminated equipment None special other than respirators and goggles.As of the date of preparation of this document, the foregoing information is believed to be accurate and is provided in good faith to comply with applicable federal and state laws.However, no warranty or representation with respect to such information is intended or given;and it is the responsibility of the user to comply with all applicable federal, state, and local laws and regulations.

http://www.schundler.com/msdsverm.htm 05/18/2006 ALION-CAL-VA-2739-O0 Rev. 3 VERBMCULJTE MATERIAL SAFETY DATA SHEET-- SCHUINDLER COMPAAihrnent FNV

OF Back to Main & v http://www.

schundler.com/msdsvenn.htm0 05/18/2006 ALION-CAL-TVA-2739-03, Rev. 3 ZI\&osLu " S ci I Attachment F, Page 18 of 40 Bypass Fraction Determination Input 1. Representative Fiber Diameter of Long Fiber: 15 microns (ref. 1)2. Representative Fiber Diameter of Medium Fiber: 10 microns (ref 1)3. Representative Fiber Diameter of Short Fiber: < 5 microns (ref. 1)4. Number of fibers (ref 1)5. Long Fiber Length: 1100 microns (ref. 1)6. Medium Fiber Length: 300 microns (ref 1)7. Short Fiber Length: 100 microns (ref 1)8. Fraction of fibers at varying lengths (ref. 1)9. Flow rate: 68.2 gpm (ref 2)10. Density of Min-K: a. Bulk density = 16 lb/ft 3 (ref. 3)b. Particle density = 165 lb/ft 3 (ref 3)11. Density of Nukon (latent fiber)a. Bulk density = 2.4 lb/ft 3 (ref. 4)b. Particle density = 175 lb/ft 3 (ref 4)12. Density of 3M-M20C: a. Bulk density = 39 lb/ft 3 (ref. 3)b. Particle density = 175 lb/ft 3 (See assumption 5)13. Mass quantities used from Table 3 of ref. 2 a. 3M-M20C (total) = 1.3 Ibm b. 3M-M20C (fiber) 0.715 Ibm (1.3

55%) -See assumption 6 c. 3M-M20C (particulate)

= 0.585 Ibm (1.3

45%) -See assumption 6 d. Nukon (latent fiber) = 0.15 Ibm e. Min-K (total) = 0.20 Ibm f Min-K (fiber) = 0.04 Ibm (0.20*20%)

g. Min-K (particulate)

= 0.16 Ibm h. Silicone carbide = 4.60 lbm (used to simulate phenolics, alkyds and silicone coatings failed as 10 micron particulates)

i. Tin powder = 2.20 Ibm (used to simulate inorganic zinc failed as 10 micron particulates)

j. Dirt/Dust

= 0.60 Ibm Assumptions

1. Average diameters and lengths of fibers are representative.

Technical Justification:

This is a reasonable assumption and is based on data from NSL Labs. Further characterization of each individual fiber is very time intensive and would not be expected to produce a significant difference in the results.2. Samples 4, 5 and 6 fiber lengths and diameters are assumed to be the same length and diameter as sample 3 fibers.Page 1 of 4 ALION-CAL-TVA-2739-03, Rev. 3 ES 0 -, : ., Attachment F, Page 19 of 40 Bypass Fraction Determination Technical Justification:

This a reasonable assumption based on the data from samples 1, 2 and 3. Furthermore, one would expect that as fibers recirculated, the longer fibers would collect on the strainers and shorter fibers would bypass.3. Sample 3 medium fiber diameter is assumed to be 10 microns.Technical Justification:

The sample 3 medium fiber is 5 microns. However, for simplicity, it is assumed to be the same diameter as sample 1 and 2 medium fibers. This is conservative since the larger diameter will result in a greater quantity of fiber bypassing and does not significantly affect the particulate bypass quantity.4. 20% of MMi-K is fibrous while the remaining 80% is in particulate form (ref 3).5. Particle density of 3M-M20C is 175 lb/ft 3 (ref. 4 and 5).Technical Justification:

Since 3M-M20C is assumed to behave as Low Density Fiberglass Insulation (LDFG) in the debris generation calculation (ref. 3), its particle density is assumed to be equivalent to Nukon.6. 55% of 3M-M20C is fibrous while the remaining 45% is in particulate form.Technical Justification:

The MSDS for 3M-M20C (ref. 6) shows that the composition of the insulation is made up of 40-60% vermiculite, 10-15%aluminum silicate, 5-10% organic binder, 5-10% metal foil, with the remaining 5-40% is not specified.

Vermiculite and the metal foil are not fibrous materials and are treated as particulates.

Using a conservative approach, the particulate components are minimized resulting in 45% of the 3M-M20C treated as particulates.

The organic binder, aluminum silicate and unknown material are assumed to be 100% fibrous resulting in a maximum value of 55% fibrous component of 3M-M20C.Methodology Fibrous Debris Bypass Fraction Bypass Fraction of Fibrous Debris was determined by calculating the total volume of fibers for each sample using the fiber lengths, diameters and total number of each fiber type (long, medium, short).Volume/25 ml (ft 3/25 ml) = Total Number Fibers/25 ml * [(AL

LL * % Long) +(AM

LM * % Medium) + (As

Ls * % Short)]where AL = Cross Sectional Area Long Fiber (ft)AM = Cross Sectional Area Medium Fiber (fi)As= Cross Sectional Area Short Fiber (Ri)LL = Length of Long Fiber (ft)LM Length of Medium Fiber (fl)Ls Length of Short Fiber (ft)The total fiber volume was then converted to mass/25 ml by multiplying the volume (ft 3)/25 ml and the total material density (lb/fl 3). The material density was calculated Page 2 of 4 ALION-CAL-TVA-2739-03, Rev. 3---Attachment F, Page 20 of 40 Bypass Fraction Determination using the particle densities of each type of fibrous material weighted by percentage of total quantity in the test.The total mass was calculated by determining the mass/min for each sample and then mass/10 min (time between samples).The strainer test was performed for a minimum duration of approximately 50 minutes which is the calculated time for the water in the flume to recirculate 5 times. The data for fibrous debris was then plotted to determine the exponential trendline equation.Integration of the trendline equation y = 8.685E-4 exp (-3.963E-2 x) from 0 to infinity gives a total quantity of 0.0219 Ibm.Using an alternative method (Riemann sums), the mass/10 min values were summed for the total quantity of fibrous debris measured in the bypass sample. However, use of the exponential trendline resulted in a greater bypass fraction and thus is conservative.

The bypass fraction is the total mass of measured fibers that bypassed the screens divided by the total mass of fibrous debris introduced upstream of the strainers.

Particulate Debris Bypass Fraction A similar methodology that was used to determine the fibrous debris bypass fraction, is employed to determine the particulate debris bypass fraction.Since the samples are already given in weight, the total mass of all debris is calculated.

The mass of the fibrous debris is subtracted from the total mass to give a total mass of particulate debris.Three methods could be used to determine the total mass of particulate debris. Using a Riemann sums method, integrating a linear trendline from zero to a calculated depletion time of 69.2 min or integrating the exponential trendline from zero to infinity gives considerably different results. However, depending on the resulting application, the conservative value could be the minimum value of 39% using the Riemann sums method or 60% by integrating over the exponential trendline.

The linear integrated value of 49%particulates bypassing the strainer is provided as well. Thus, these values are determined by this evaluation with the end user responsible for determining which is the appropriate value for the applicable application.

The bypass fraction is the total mass of particulate debris that bypassed the screens divided by the total mass of particulate debris introduces upstream of the strainers.

Page 3 of 4 MAY-18-2006 12:38 Results TUAN Procurement B Frc tion- 3 Dtcf 9ricai 7 Bypass Fraction Determination 42AtLTacmentFA-27Page1fRK 3 Attachment F, Page 21 of 40 As shown on Worksheet A, the fraction offibrous debris that bypasses the st ner was 2.42%.As shown on Worksheet B, the fraction of particulate debris that bypasses the~strainer was a minimum of 39% and maximum of 62% and a mid-range value of 49%.Depending on the application, the end user will determine the appropriate value to use.References I. FANP Document No. 38-9013790-000, NSL Ainalyrical Test Reprt'2. FANP Document No. 51-90088451-002, Test Report for SURE-FLOWTO Strainer Performance Test for Watts Bar Nuclear 3. ALTON-CAL-TVA2739-03, Rev. 1, Watts Bar Reaction Building GST-191 Debris Genefation Calculation

4. NRC Final Draft SER, Safety Evaluation by the Office of Nuclear Reattor Regulation Related to NR.C Generic Letter 2004-02, Nuclear Energy Iristitute Guidance Report, "Pressurized Water Reactor Sump Performance Methodology", Appendix V,Section V. 1. 1 5. NTRC Final Draft SER, Safety Evaluation by the Office of Nuclear Reactoi Regulation Related to NRC Generic Letter 2004-02, Nuclear Energy Institute Guidance Report, "Pressurized Water Reactor Sump Performance Methodology", Section 3.5.2.3 6. Material Safety Data Sheet for INTERAM(tm)

M-20A .AND M-20 AND IM-'20C MAT. ISSUED: April 12. 1999. DOCUMENT:

10-8339-3 ,1 I'II,, Prepared By: Cynthia M, Maples Tennessee Valley Authorit'Reviewed By: Doug M. Pollock Tennessee Valley Authority Dite: 5-18-06 Date: 5-18-06 TOTAL P.01 Page 4 of 4 WATTS BAR BYPASS FRACTION TESTING WORKSHEET A -FIBROUS DEBRIS BYPASS CASE TIME COUNTI LENGTH VOLUME MASS nin ý pr25 m2 I % Ion % medium % hort ft, lb25 ml ib/ft3 lb/min lb/i10 min rest 2A 10 290 6% 71% 16% 3.A09E-10 5.427E-08 6.147E-05 5.604E-04 0.0056 Test 3A 20 195 8% 75% 17% 2.311E-10 4.034E-08 4.569E-05 4.165E-04 0.0042 Test 4A 30 290 8% 75% 17% 1.778E-10 3.103E-08 3.515E-05 3.204E-04 0.0032 Test 5A 40 109 8% 75% 17% 6.681E-11 1.166E-08 1.3 2 1 E-05f 1.204E-04 0.0012 Test 6A 50 131) 8% 75% 17% 7.969E-11 1,391E-08 1.576E-05 1.436E-04 0.0014-Sample in flume and not taken via bypass sampling ports Representative Fiber Diameter (Long)15 micron 4.9213E-05 ft Cross Sectional Area 1.902E-09 It Representative Fiber Diameter (Medium)10 micron 3.2808E-05 ft Cross Sectional Area 8.454E-10 It'Represenlative Fiber Diameter (Short)5 micron 1.6404E-05 ft Cross Sectional Area 2.113E-10 ftV Flow Rate 68.2 gpm Flow Rate 9.12 ftl/min Material Density 174.56 WW Total Ib 0.0156 0.0219 Riemann sum Integrated trendline Integrated Bypass Total -Fibrous Debriq 1.73%1 2.42%V Fiber Depletion During Test y z 8.685E-04e-3-29 'Total Ilber 0.905 Ibm%3M 79.01%% mmn-k 4.42%% nukon 16.57%Bulk Density Particle Density Ib/cu. ft.39 175 16 165 2.4 175 E0.0 U.t

..--6.OOOE-04 5,000E-04 A 4.000E-04 3.000E-04 2.000E-04 1.00012-04 O.0002+00 0Z C'TA Fiber Length Long Medium Short 1100 micron 3.609E-03 ft 300 micron 9.843E-04 ft 100 micron 3.281E-04 ft 0 50 100 150 200 250 300 350 Time (rain)ID CD -,j r')C o40 (D WATTS BAR BYPASS FRACTION TESTING WORKSHEET B -PARTICULATE DEBRIS BYPASS CASE TIME Total Sample Weight MASS m min I g/er 25 ml lb/25 ml lb/ftA3 lb/min b/O min...... Not.used Test 2A 10 0.0045 9.9206E-06 1.124E-02 1.024E-01 1.0245 Test 3A 20 0.0036 7.9365E-06 8.989E-03 8.196E-02 0.8196 Test 4A 30 0.0027 5&9524E-06 6.742E-03 6.147E-02 0.6147 Test 5A 40 0.0022 4.8501E-06 5.494E-03 5.009E-02 0.5009 Test 6A 50 0.0014 3.0864E-06 3.496E-03 3.187E-02 0.3187 Total Total Minus Fiber 3.2783 lb 3.2564 lb Fiber Mass 0.022 lb Flow Rate 68.2 gpm Flow Rate 9.12 ft 3/mir'S Ck~Integrated Bypass Total -Particulate Debrisl 39.98%Total Total Minus Fiber Using exponential trendline 5.0106 lb 4.9887 lb Integrated Bypass Total -Particulate DebrisI 61.25%/Total Mass 8.145 lb Totally depleted in 69.12 min Total Total Minus Fiber Using linear trendline 4.0607 lb 4.0387 lb Integrated Bypass Total -Particulate Debrisl 49.59%1 (O3 r> .W T 2,0 (DF Particulate Depletion During Test I----Seres1

...... Expon. (Seriesi)

---Linear (Series1)

I y = 0.1418e-0 0 2 1 3 x.,~ ~4l S8.OOOE-02 U)6.0OOE-02 0'E'U CL 2.OOOE-02 C. OQOE+00 0 10 20 30 40 50 60 70 80 Time (min)I-PO 0) CD)CD ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 25 of 40'I-tCi (G A AR EVA Document Number: 51-9008451-002 ATTACHMENT-3 FANP Document No. 38-9013790-000 WATTS BAR STRAINER PERFORMANCE TEST DOWNSTREAM BYPASS RESULTS FmitreANP, Inc., an AREVA and Siemens company e A -~ le ALION-CAL-TVA-2739-03, Rev. 3 9 / &A~ttachment F, Page 26 of 40 (THU) DEC 15 2005 17:06/ST.

17:05/NO.

6309524074 P 1 51-9ooSf - ooz FROM A *ANALYTI CAL Farlba Gartland, PMP P'oject Manager El FRAMATOME ANP, Inc.An AREVA and Siemens Company 7207 IBM Drive, CLT-2A Charlotte, NC 28262 Date: 12/15/05

Dear Fariba,

We have completed the analysis of the seven samples submitted on December 5th using methodology that was discussed and agrced -upon between NSL and Framatonc.

Details of the method are listed below.Insoluble Solids content 1. Three 25ml portions of the well-shaken sample were extracted and filtered through a weighed ,45 micron nitrocellulose filter for each individiial sample.2. Sample filters were then dried at 105 degrees centigrade for approximaiely 20 minutes and weighed again after cooling.3. Insoluble solid values were calculated from the weight difference for each filter and the average of the three analyses was reported.Ate I. C1 I It if ,ýýýP, rividw I 7650 Hub Pikway -CIlvc~and, Ohio 4412; -Of-e: 216-447-1550

F=x:216.447-0;16 -web Site: wwndrnluyt~ical conm V% A3 ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 27 of 40 C,:6 3 jc, 4 e- ,-/ rX -3, c, .r / 1P FROM P JSL A L (THU)DEC 15 2005 17:06/ST, 17:05/NO.

6309524074 P 2 S I- q cosy l-oo2.Fiber count and length 1. Filters containing fibers and particles from prcvious test were used for the testing of fiber counts and length, 2. Preliminary light microscope observations were ustd to determine fiber location on the filter surface. Useful magnification is 100-200X 3. Collection of fibers was accomplished by using sticky carbon tape or other sticky conductive rmaterial.

Tape was pressed against the filtet and repeated as many times as needed to collect fibers fully from filter surface, Fix carbon tape on SEM stab.4. A light microscopic observation of filter surface was performed to ensure complete fiber collection.

5. Tape containing fibers were examined by scaming electron microscopy coupled with energy-dispersive X-ray spectroscopy (SEM!EDS) and PMS (Particle Measurement System) for count completion, Magnification varied depending on'fibers size, 6. The longest and shortest fiber from each filter was measured and an average of each class of the throe samplings was reported in millimeters.

7. Each individual filter was examined and all fibers were counted with the average of the three reported for the total fiber count, Please let me know if you need any additional information regarding the analysis or the final results.Regards, David Kluk Technical Manager NSL Analytical Services 7b50 HO Ptrkwty , C*IvdOW0bb 4412 fl .Z 16-447-10500

-Fit; 21b44?,0716 " VWb Site;

?ý A4- I INSL S'ANALYTICAL y .V~f/4, ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 28 of 40 ISO/IEC Gode 17025 TEST REPORT THE REPORTED TEST RESULTS ONLY TO THE ITEM(S) TESTED Framatome ANP (Charlotte) 400 South Tyron St Suite 2100 Charlotte NC 28285 0 Attn: Fariba Gartland Client

Description:

Water NSL Lab No: 0524811 Tests Fiber Count Longest Fiber Size Date: 1211212005 Report No-: 139090 C3 0 C)Page: I of 1 Sample 10- Sample iA Background sample from Flume 6" Town Water No Debris 11129105 Results/Unitso not detected not detected not detected Methods SEM SEM Shortest Fiber Size Total Sample Weight SEM 0.0003 gr.25 Iml Wet Chemistry Reporting Officer: --FR 1 Carm D'Agostino, Wet Chem Supervisor THIlS REPORT IS CONFIDENTIAL AND INTENDED FOR THE ADDRESSEE ONLY, IF YOU RECEIVE IT IN ERROR, YOU ARE PROHIBITED FROM OISCLOSINO, COPYING. DISTRIBUTING OR USING AN.OF THIS INFORMATION.

PLEASE CONTACT OUR OFFICE FOR INSTRUCTIONS.

THE INFORMATION AND DATA IN THLS REPORT ARE RENDERED UNDERTTHE CONDITIONS OUTLINED IN THE T'IERMS AND CONOITIONS APPEARING ON THE BACK OF THE CERTIFIED REPORT. THE RECORDING OF FALSE, FICT IlOUS OR FRAUDULENT STATEMENTS OR ENTRIES ON TIS DOCUMENT MAY BE PUNISt'D AS A FELONY UNDER THE1 FEDERAL STATUTES INCLUDING FEDERAL LAW, TIlrIE Il. CHAPTER 57.

(/ f~fL~fI'SNSL' oANALYTICAL ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 29 of 40<; -.q o% Si--ooZ SEAccGudre d IrO0AEC Guide 17025 TEST REPORT THE REPORTED TEST RESULTS RELATE ONLY TO THE ITEMS) TESTED Framatome ANP (Charlotte) 400 South Tyron St Suite 2100 Charlotte NC 28285 0 Attn: Fariba Gartland 0 Client

Description:

Water Date: 12112/2005 Report No.: 139080 0 P 0 0 Page: 1 of 1 NSL Lab No: 0524802 Tests Fiber Count Longest Fiber Size Shortest Fiber Size Total Sample Weight Sample ID: Sample 1A 11:42 11/29105 ResultslUnits0 303125 ml 3.8 mm 0.15 mm 0.0072g/25ml Methods SEM ,SEM SEM Wet Chemistry Reporting Officer: FR 1 Carm D'Agostino, Wet Chem Supervisor THIS REPORT IS CONFIDENTIAL AND INTENDED FOR THE ADORESSEE ONLY. IF YOU RECEIVE IT IN ERROR YOU ARE PROHIBITED FROM DISCLOSING.

COPYING. DISTRIBUTING OR USING ANN OF THIS INFORMATION.

PLFAAF CONTACT OUR OFFICE FOR INSTRUCTIONS.

THE INFORMATION AND DATA IN THIS REPORT ARE RENDERED UNPER 'HiE CONITIONS OUTLINED IN THE TERMS AND CONOITIONS APPEARING ON THE BACK OF THE CERTIFIED REPORT. THE RECORDING OF FALSE, FICTITIOUS OR FRAUDULENT STATEMENTS OR ENTRIES ON THIS DMUMENT MAY BE PUNISHED AS A FELONY UNDER THE FEDERAL STATUTES INCLUDING FEDERAL LAW. TITLE 18. CHAPTER 57.

FROM ALION-CAL-TVA-2739-03, Rev. 3--4-" ifoJ t. ,. C/ , & cf" /10,,, Attachment F, Page 30 of 40 (t 6 0 -(MON)FEB 13 2006 13:18/$T.

13:18/N0.

6309524908 -PF 1 TEST REPORT ZHE REPOHTW TeIT RFrEM'Tr IRELATIE A ONLY TO iHE 1iFAS) YESTf J ,AEC4nde t?025 Fmnmstame ANP (ChalaoUs) 400 SoMo Vlyn St SUite 2100 Charlaif NO 28285 Aun: Faribe GirUand Revimad R.eport Sample DIscriptOn Correi:d GlIent DOWIpton.l:

TVAJ FlumeWaft DMi 2W2006 Repadt No.: 13906 Page: 1 of 2 NSL Lab NO: 0524802 tests Average Diameter of Long Average Diameter of Medium Average Diameter of Short Fiber Count% Long Long Fiber Length% Medium Medium Fiber Length Short Short Fiber Length Sample ID; Sample 1A 11:42 11)2M/05 ResultsUnits Methods 15miorons SEM 10microns SEM<5mlcrons SEMml SEM 13% SEM 1100microns SM 77% SEM 300miorons SEM 10% SEM 100microns SEM Ofiew.R ICarm D'Agostino, Wet Chem Supervisor TH15 LAQIDE N D MR THEAOM755,5 ONLY- F YOU R&C*rtv T Dv E80O YOU A9 Pa Mu #o DtswaO , ooY No, O U=No Am Or mTIS lMrUAi. ftRAW 0)4TACT "0R 1FE FOR I4BTRUCTIO*4 THE rWORMAfTlQ AND DATA IN THIs poaPq r4 ARsE vmR5--R 7)45 CO NSom a0"nihNEo The-MAW ANO =40NIfONUr APIPe.N3 O]N TM XR OC. tCR'lHED HL"OR t. Y"11 QE-- OF FAL5, iICITIO4US OR 4'ATwI NT* 9R " N TX4 DQ;-QLME MAY N PlVNM AS A ;ELW UNMR IM 3IJTES INCWLUM FERA_. LAW, IlnJE Iit CKPATER 57.~A 3-~

ALION-CAL-TVA-2739-03, Rev. 3 FROMfc ýj .-< s/ -7 o /r , Attachment F, Page 31 of 40 FROM ' ?(MON)FEB 13 2006 13:18/ST.

13:18/NO.

6309524908 P 2 TEST REPORT gr' AN 3LTTHE REPOE UAT SFU° RELATE ANALYTICAL.

.50AEC Oudo 17 Framtolft ANP {(ha1otto) 400 South Trymn St Suit. 2100 CON.rllte NC 28285 Attnk Failba Garidlwi Rervised Repoal Sample ODiptlo Corrected Client Iae otpwlot TVA/ Plume-Watts Report No.- 139080 Page: 2 of 2 NIL Lab No- 052480S Tests Total Sample Weight Sample ID: Samflple 1A 11:42 1129/05 Reaultwunis O.O072g/2fm1 MethWds Wet Chemirtry/Reportig Officer Sf Carm D'Agostlno,Wet CNem Supaervisor THIS REPOA M 0MOW0MXJE1 NO WN7M=f PON fl49 AIWOACS ONLY. df V'OU WCVV rr N4 ERROR, YOU AR Pft6zn= OM OcWn,6Io coPn"G D(5T~I9UT1Q OR USINGANV 6DMUTP RISSOk& 14 LESCO*Acr(.7LA-FeIC OP WRUCTQWE TlIEP4VMAPOArdNAC ATA *4 ThS POFFTAJ1E EERED WO~f -me COIITIOJ fltflEwdIIIth I......N..C....EA..t......COT

.....g.R.PORI THE PREOO. OF FA=SE.

ca FRAuD"OIElNTJK'.MN oR EKTrIE3 Oa TMIS OocI.wNT WAY W PUMM AS AAELOKY UWHM ThE ARsLSTA7nTES MWMjjrvO FMEAPUJL.AW.,TI 1% , TEIR S7.

e(1CIte 9 7S 'f/INSL V ANA LYTI CA L ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 32 of 40 gI

S 4 -00 2-.Q Ac c reditId I0SOAEC Gu;de 1702-S TEST REPORT THE REPORTED TEST RESULTS RELATE ONLY TO THE ITEM(S) TESTED Frarnatome ANP (Charlotte) 400 South Tyron St Suite 2100 Charlotte NC 28285 0 Attn: Fariba Gartland D 0 Client

Description:

Water Date: 12112/2005 Report No.: 139082 0 0 P 0 0 0 Page: 1 of 1 NSL Lab No: 0524803 Tests Fiber Count Longest Fiber Size Shortest Fiber Size Total Sample Weight Sample ID: Sample 2A, Test 1A, Time 11:52 Results/UnitsD Methods 290125ml SEM 2.47 mm SEM 0.07 mm SEM 0.0045g/25ml Wet Chemistry Reporting Officer: ____._FR1 Carm D'Agostino, Wet Chem Supervisor THIS REPORT IS CONFIDENTIAL AND INTENDED FOR THE ADDRESSEE ONLY. IFYOU RECEIVE IT IN ERROR, YOU ARV PROIBITED FROM DISCLOSING, COPYING, DISTRIBUTING OR USING ANN OF THIS IINFORMATION.

PLEASE CONTACT OUR OFFICE FOR INSTRUCTIONS.

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L-- ALION-CAL-TVA-2739-03, Rev. 3 V o- >f Attachment F, Page 33 of 40 FR ON S!-q6o0 ,l+i- 002 (M0N)FE3 13 2006 13-:18/ST.

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6309524908 P 3 TEST REPORT 'A d Ced I hE 1EST R=SILTV RLA E-ANLV 3 LO4. TO THE .WSI d A ALYT7CAL iO. GL 7Z Promutm AN P (Chadote)4o0$outh ryron St Su.te 2100 Charlotte NC 20905 Aim! Fadba a&lnd ReviP d Report: Sample DIwApdlan and Unito Cornred Cliewt Osauoptlon:

TVAJ PFlne-Watb Date: 202006 Report No., 1390M Pager I Of 2 N$L Lab No: 0524808 Tests Average Diameter of Long Average Dienmeter of Medium Average Diameter of Short Fiber Count% Long Long Fiber Length% Medium Medlum Fiber Length% Short Short Fiber Length Sample 1D: Sample 2A, Tftt 1A, Time 11:52 Resulte/Unita Methods 15microns SEM lOmicrons SEM SEM 290025rn1 SEM 6% SEM 1100microns SEM 78% SEM 300mioronrs SEM 16% $EM 100microns SEM Iepovleg Officer, FRI Catm.O'Agostno, Wet Chem Supervior OETh IF.PA CT/ OR AE FORR, m S,,z .IthE- INF M OATA IN TH8 AER T IIr EMR~ OUTILIm:O IN mlJ THIS AM O WT RAPSIGONTELCKO HECRAS POT.TEA RXGOFF1E.9Of G9O PAIUIETEA TO FrME O h DEEM MA 7 18CNOA EO( M)R15FKRL Tlj~gI~(l ES~.LWTT.

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6309524908 P 4 7"E REPORTED Y IS7 oI*,GuLT

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MethOds Wet Chemistry Rep~ritng 0ffloer_: R i O Carm D'Agostino, Wet Chem 8uervisor THI" PEPORT I CONI nA ANM O INMTNDW MOR 7' ABORESSC OYTI .PYO, FEMME fr IN EMA, YO PROTTRMRI'ROI OW6 CC.'Y1W. OIS TI.O On US*M AM OFTHISINPORIVIAM.

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-702-iSO/7EC Guide 77I 725 Framatome ANP (Charlotte) 400 South Tyron St Suite 2100 Charlotte NC 28285 0 Attn: Fariba Gartland C 0 U Ciegnt

Description:

Water NSL Lab No: 0524806 Tests Fiber Count Longest Fiber Size Shortest Fiber Size Total Sample Weight Date: 12/12J2005 Report No.: 139085 0 0 0 0 Page: 1 of I Sample ID: Sample 3A, Test 1A, Time 12:02 Results/Units0 Methods 195/25 ml SEM 2.23 mmr SEM 0_07 mm SEM 0.0036g/25ml Wet Chemistry Reporting Officer: FRI Carm D'Agostino, Wet Chem Supervisor THIS REPORT ISCONFIDENTIAI.

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ALION-CAL-TVA-2739-03, Rev. 3.- / ., o ,Z" hment F, Page 36 of 40 FROM -(MON)FEB 13 2006 13:18/ST.

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6309524908 P 5 TEST REPORT THE REPORTED TEST RE uTS RMETCTE 1 oftyI* TOE ?I4 oke ri.1:0 1"LC UEO l-*ANALYTICAL Fni.MmeU ANP (Chaflt.M)

Date! 2(SMON 4" souh Tymn st Suits21o-Chafeetaf NC 28285 R No- 139068 Anin! Parlbe Cwtland Supplemerdal FRpait: Other Woru Pee1mnrad Cllu4 TVAJ Flume-Watt Page: 1 of 2 NSL Lab No: 0524806 Tests Average Diameter of Long Average Diwmeter of Medium Averatge Diameter of Short Fiber Count% Long Long Fiber Length% Medium Medium Fiber Length%Short Short Fiber Length Sample ID: Sample 3A, Test 1A, Time 12:02 Remuftnltsnn Methods 15microns SEM smicrone SEM<'m5cro" SEM 195(25 ml SEM 8% SEM g00microns SEM 75% SEM 300microns SEM 17% SEM t00mlcrons SEM Reporting Officef: FA Carrn D'Agooft .Wet Chem Supervisor nW ~O R M LU GIf OENIDWK AND 141?CE F~OR THE ADDRE88M ONLY. F YOU RL2EM r1`01 MRMO. VWU AAR pAOWMLUDFROM OWELSN.OPNG ITU1EORUHAU OF THIS HFOWTAWN.

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13:16/NO.6309524908 P 6 TEST REPORT A , 1*6 AN Z L hE .R.TI TEST ARLTS RELATE 6W , ONLY TO THE rmTEI) Tc6mo LSOAEC GLOWe 17P 0ANALYTICAL F!nluome ANP (Chulofte) 400 South Tyron St Suite 2100 Chador NO 26285 AtMn; Fmdbe Gastiand Supplemental Repfrtt Other Wo*c Performed Client Denriptinn:

TVA/ Flume-Watis Da2 /W2006 Fleport No.: 130085 Page: 2 of 2 NSL Lab No: 0624008 Tests Total Sample Weight Sample ID: Sampte 3A, lest 1A, Time 12:02 Results/Units Methods 0.O036gd'25m1 Wet /Reporting Officer: FRI Carm DAgostifio, Wet Chem SupervsorHE~ANTO I NI IT EAS CO TATOU OFK FO I4BT ;RUCTIN lHE IHE-ORMA?, 10rNA1i OATA IH 1T1,S AtPlrT ARE i ENDiTREC3 1)- Nl11N IN ml IwAy 8- PUNlIW4ED AB8A FEOR, STATUI]ES AI.U0NG PECERAJ.L AW, TIlT! lB. OHAPTER 57',

SNSL~WANALYTICAL Framatome ANP (Charlotte) 400 South Tyron St Suite 2100 Charlotte NC 28285 ED Attn: Fariba Gartland 0 D 0 Client

Description:

Water ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 38 of 40 TEST REPORT A .ccred ,e d THE REPORTED TEST RESULTS RELATE ONLY TO THE ITIN(Sj TESTED ISO.EC Guide 17025 Date: 12/1212005 Report No.: 139087 0 C 0 0 Page: 1 of I NSL Lab No: 0524808 Tests Fiber Count Longest Fiber Size Shortest Fiber Size Total Sample Weight Sample ID: Sample , ResultslUnitsD 290/25 ml 1.27 mm 0.06 mm 0.0027gl25ml IA, Test 1A, Time 12:12 Methods SEM SEM SEM Wet Chemistry Reporting Officer: FRI Carm DAgostino.

Wet Chem Supervisor THIS REPORT IS CONFIDENTIAL AND INTENDED FOR THE ADDRESSEE ONLY. IF YOU RECEIVE IT IN ERROR, YOU ARE PROHBITED FROM DISCLOSING, COPYING, DISTRIBUTING OR USING AN)OF THIS INFORMATION.

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ANSL ANA L.VTICAL TEST REPORT THE REPORTED TEST RESULTS RELATE ONLY TO THE ITBEI(S) TESTED ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 39 of 40 SO/tEEC Guide 17025 Framatorne ANP (Charlotte)

Date; 12112/2005 400 South Tyron St Suite 2100 Charlotte NC 28285 Report No.: 13908 0 0 Attn: Fariba Gartland D L 0 O U Client

Description:

Water 0 Page: 1 of 1'9 NSL Lab No: 0524810 Tests Fiber Count Longest Fiber Size Shortest Fiber Size Total Sample Weight Sample ID: Sample 5A, Test 1A, Time 12:22 Results/Units 0 Methods 109/25 ml SEM 1.45 mm SEM 0.10 mm SEM 0.0022g/25ml Wet Chemistry Reporting Officer: FRI Carm D'Agostino, Wet Chem Supervisor THIS REPORT IS CONFIDE NTIAL AND INTENDED FOR THE ADDRESSEE ONLY. IF YOU RECEIVE IT IN ERROR, YOU ARE PROHIBITED FROM DISCLOSING, COPYING. DISTRIBUTING OR USING ANI OF THIS INFORMATION.

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/h~5j~~ (/f;~' /,f/~, INSL SANALYTICAL ALION-CAL-TVA-2739-03, Rev. 3 Attachment F, Page 40 of 40 ISO/IEC Guide 77025 TEST REPORT THE REPORTED TEST RESULTS RELATE ONLY TO THE IrEMWS) TESTED Framatome ANP (Charlotte) 400 South Tyron St Suite 2100 Charlotte NC 23285 0 Attn: Fariba Gartland 0 0 Client

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Water NSL Lab No: 0524805 Tests Fiber Count Longest Fiber Size Date: 1211212005 Report No.: 139084 P 0 Page: 1 of 1 Sample ID: Sample# 6A Time: 12:32 11129105 Results/Unitso 130/25ml 1.33 mm Methods SEM SEM Shortest Fiber Size Total Sample Weight 0.05 mm SEM 0.0014g/25ml Wet Chemistry Reporting Officer: R Carm DAgostino, Wet Chem Supervisor THIS REPORT IS CONFIDENTIAL AND INTENDED FOR THE ADDRESSEE ONLY. IF YOU RECEIVE IT IN ERRCR, YOU ARE PROHITED FROM DISCLOSING, COPYING, DISTRIBUTING OR USING ANI OF THIS INFORMATION-PLEASE CONTACT OUR OFFICE FOR INSTRUCTIONS.

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WWatts Bar Reactor Building GSI- 191 Debris Generation Calculation Document No: ALION-CAL-TVA-2739-03 Rev:3 Page: G-l of G-9 ATTACHMENT G -MIN-K This Attachment contains emails from Thermal Ceramics and Microtherm International stating the composition of microporous insulation along with the Min-K data sheet as provided by Thermal Ceramics.

Thermal Ceramics ALION-CAL-TVA-2739-03, Rev. 3 Attachment G, Page 2 of 9 Flexible Min-K Flexible Min-K is a composite system consisting of a microporous core encapsulated between layers of high temperature cloth and quilted in 1" squares. The quilting maintains core distribution in high vibration environments and allows the insulation to be wrapped or bent to conform to unique geometric shapes during installation.

Product thickness, core density and composition, and cloth selection vary with application.

Flexible Min-K Options Core formulations

.......................

F-150 (1200'F),F-182 (1832'F)Cloth facings ................

2116 E-Glass (500°F), S-Glass (1200'F)503 Quartz (1958°F), 593 Quartz (1958°F)Nextel T M (2200-2500°F)

D ensity, pcf* ..................................................................

8, 10, 16 Thickness, in ........................................................

./8, Y/4, I/N6, 3/% , 1/2 0.50 thick material available at a maximum of 14 pcf Standard Tolerances Thickness

..............................................................

+ 0.060/- 0.030 Length and Width, Fabricated parts ................................

+/- 0.125 Length and Width, Standard sheets ...........................

+ 2.0/- 0.00 Standard Flexible Min-K Offerings High temperature composition, rated at 1832°F* 1801/8 ....................

Quartz 503 cloth, F182 core, 8 pcf density* 1801/10 ................

Quartz 503 cloth, F182 core, 10 pcf density* 1801/16 ................

Quartz 503 cloth, F182 core, 16 pcf density Mid-range composition, rated at 1200°F* 1201/8 .........................

S-Glass cloth, F150 core, 8 pcf density-1201/10 .....................

S-Glass cloth, F150 core, 10 pcf density-1201/16 .....................

S-Glass cloth, F150 core, 16 pcf density Standard composition, rated at 500°F*501/8 ..................

2116 E-Glass cloth, F150 core, 8 pcf density*501/10 ..............

2116 E-Glass cloth, F150 core, 10 pcf density*501/16 ..............

2116 E-Glass cloth, F150 core, 16 pcf density Wariations of the cloth facing, hot or cold, core material, thread, and density are avail-able.Material is supplied in 3' x 3' or 4' x 3', square stitched (1"centers) sheets. Fabricated strips, referred to as tapes, are available in widths of 1 ", 1/2" and 2'/2", in 6 ft lengths.Customized sheet sizes and fabricated shapes are available upon request.Product Information Features* Very low thermal conductivity

Benefits weight and space constraints" Durable" Flexible and lightweight" Composite temperature use limit ranges from 500 to 1832°F Core and Textile Facing Selection While thermal management requirements often dictate material thickness and core density, the maximum continuous use tempera-ture seen in the application is the deciding factor for core and cloth selection.

Because this is a composite material, the use limit is decid-ed by the lowest use limit associated with the materials incorporated into the design.Core: Maximum temperature use limit of the microporous core is a function of- both shrinkage and degradation of thermal con-ductivity.

At elevated temperatures, the cellular structure of the microporous insulation, which is responsible for the extremely low thermal conductivity, is compromised.

The core compo-nents, including SiO 2 , particles, metal oxides and re-enforce-ment fibers, may melt or sinter together at elevated tempera-tures increasing both the solid conduction due to material con-tact, and molecular conduction of air due to the degradation of the microporous structure.

Core Formulations" Mix F182 is utilized for temperatures up to 1832°F and where high vibration environments are seen." Mix F150 is used for applications at 1200'F and lower.Cloth: Cloth selection is based on the maximum temperature use limit required by the application, but may also be determined according to other physical characteristics such as rigidity, permeability or durability.

Some cloths (Nextel) are also used due to their qualification as an industry approved fire barrier.The maximum temperature use limit is based on the degra-dation of the strength of the material.

Some cloths are rated for higher temperature use in other industries, the use limits here reflect the survivability of the Min-K product in demand-ing aerospace environments." 2116 E-Glass -Maximum use limit of 500'F (in harsh aero-space environments) used in 501 series of materials or Standard Flexible Min-K." S-Glass -Maximum use limit of 1200°F (in harsh aerospace environments) used in 1201 series of materials or Mid-Range Flexible Min-K." Quartz 503 -Maximum use limit of 1958°F and used in 1801 (limited by core) series of materials." Quartz 593 -Maximum use limit of 1958 0 F. Offers increased durability over Quartz 503 due to increased thickness." Nextel -Maximum use limit of 2200-2500°F.

Excellent strength and durability at elevated temperatures.

Thread: Selection is based on maximum continuous use limit of the application and consistent with the cloth." E-Glass -Standard with 2116 E-Glass and S-Glass cloths." Quartz -Standard with higher temperature cloths..L421aTI 05.02/6 14-120 ALION-CAL-TVA-2739-03, Rev. 3 Attachment G, Page 3 of 9 Flexible Min-K Product Information Density Effects Low thermal conductivity associated with Min-K is due to the microporous structure of the core. The particulate and fibrous material are sized to create pores which are <0.1 um in diameter, less than the mean free path of air. By limiting quantity and motion of air particles in the pores, both conduction due to air and con-vection heat transfer is limited, thus reducing the thermal conduc-tivity. This is the basis of microporous insulation.

At lower densities there may be insufficient material to create the very small pore structure, resulting in larger pores more capable of efficient transfer of heat and increased thermal conductivity.

As the density of the microporous insulation decreases from 16 pcf, the thermal conductivity increases.

Min-K materials are engineered to provide the optimum thermal efficiency while maintaining product handling characteristics and cost.Note 1. Density greatly affects the compression resistance of the material.Note 2. Product density refers to core material and does not incorporate the cloth facings.Thickness Considerations Flexible MIn-K501' Flexible Min-K 12011 8 10 16 8 10 16 Flexible MIn-K 18011 8 10 16 Thermal Conductivity, BTU.in/hr-ft2.oF Thickness, 0.125" 200 0.23 0.21 0.20 0.23 400 0.28 0.25 0.24 0.28 600 0.34 0.30 0.28 0.35 800 0.42 0.37 0.35 0.42 1000 0.49 0.45 0.41 0.50 1200 ---0.60 1400 ---0.72 1600 ----1800 ----Thickness, 0.250" 200 0.20 0.19 0.18 0.21 400 0.25 0.23 0.22 0.26 600 0.31 0.27 0.26 0.32 800 0.38 0.34 0.32 0.39 1000 0.45 0.41 0.38 0.47 1200 ---0.56 1400 ---0.68 1600 ----1800 ----Thickness, 0.375" 200 0.19 0.19 0.18 0.20 400 0.24 0.23 0.21 0.25 600 0.30 0.26 0.25 0.30 800 0.37 0.33 0.31 0.37 1000 0.44 0.40 0.37 0.45 1200 ---0.53 1400 --0.65 1600 ----1800 ----0.23 0.27 0.33 0.39 0.47 0.56 0.66 0.21 0.24 0.29 0.35 0.43 0.52 0.62 0.20 0.23 0.27 0.33 0.40 0.49 0.59 0.22 0.26 0.26 0.26 0.28 0.28 0.32 0.31 0.30 0.38 0.38 0.34 0.44 0.44 0.39 0.52 0.49 0.44 0.63 0.58 0.52-0.68 0.61-0.79 0.71 0.20 0.23 0.23 0.23 0.25 0.25 0.28 0.27 0.27 0.34 0.34 0.30 0.40 0.40 0.35 0.48 0.45 0.40 0.58 0.54 0.48-0.65 0.57-0.76 0.67 0.25 0.27 0.29 0.32 0.36 0.41 0.47 0.56 0.65 0.22 0.24 0.26 0.28 0.32 0.37 0.43 0.51 0.60 0.21 0.23 0.25 0.28 0.31 0.35 0.41 0.50 0.59 The insulating capabilities of microporous insulation increases with increased thickness until a point of diminishing returns is eventually reached, above which added insulation provides only a marginal benefit.Adding layers of insulation, in li" increments can substantially reduce cold face temperatures.

For a more accurate representa-tion of your specific application, please contact your Thermal Ceramics Sales Representative.

Flexible Min-K is a composite of both a lower thermal conductivity microporous core and a higher thermal conductivity high tempera-ture textile, as overall product thickness increases (while textile thickness is maintained) the composite thermal conductivity will decrease.Flexible MIn-K-16pcr Cold Face Cold Face Cold Face Thickness, In. (Hot Face =800°F) (Hot Face= 1000F) (Hot Face= 1200°F)0.125 341 410 477 0.250 268 317 367 0.375 229 269 309 0.500 204 238 273 This series of heat flow analysis were competed utilizing K-Flow 1.0 to provide a baseline for product thickness selec -ton.0.50" material is only available in densities up to 14 pdt.Acoustic Characteristics Sound absorption values range from 0 to 1.0 with 0 representing no absorption (perfect reflections) and 1.0 representing 100 per-cent absorption.

Specific Heat Parameters, Hz Material, 0.25" 125 250 500 1000 2000 4000 8 pcf, F150 Core 0.025 0.032 0.066 0.272 0.331 0.253 16 pcf, F150 Core 0.027 0.025 0.060 0.157 0.355 0.306 16 pcf, F182 Core 0.028 0.028 0.052 0.132 0.322 0.258 Data for select Min-K Microporous insulation systems via ASTM 1050.Temperature, 'F Specific Heat (BTU/Ib'F) 100 0.18 400 0.23 800 0.26 Effects Of Moisture Microporous insulation consists of a core which uses a standard grade, fumed silica as a key constituent.

Due to the surface chem-istry of the fumed silica, it absorbs moisture either through contact with water, fluids, or humidity in the air. When direct contact with fluids occurs an irreversible, catastrophic degradation of the micro-porous structure occurs, which degrades the low thermal conduc-tivity of the material.

Upon drying, it will not be restored.Flexible Min-K submerging water tests (5 minutes) and then allow-ing it to dry results in approximately a 35% increase in thermal conductivity.Testing has shown that when exposed to an environ-ment of 75% humidity for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Flexible Min-K experienced a weight gain of <5% and an increase in thermal conductivity of approximately 4%. The effects of moisture may become a concern where high humidity and heat for long duration exist.0.20 0.22 0.26 0.32 0.37 0.45 0.55.0.22 0.22 0.24 0.24 0.26 0.26 0.33 0.29 0.39 0.34 0.44 0.39 0.53 0.47 0.64 0.56 0.75 0.66 1. Ff50 core, E-Glass facing, 8,10,16 pci density 2. FI50 core, S-Glass facing, 8,10,16 pcf density 3. F182 core, Quartz 503 facing, 8, 10, 16 pcf density The values given herein are typical average values obtained in accordance with accepted test methods and are subject to normal manufacturing variations.

They are supplied as a technical service and are subject to change without notice. Therefore, the data contained herein should not be used for specification purposes.

Check with your Thermal Ceramics office to obtain current information.

Thermal Ceramics is a trademark of The Morgan Crucible Company plc. BTU-Block and Min-K are trademarks of Thermal Ceramics Inc.Marketing Communications Offices Thermal Ceramics Americas T: (706) 796 4200 F: (706) 796 4398 Thermal Ceramics Asia Pacific T: +65 6733 6068 F: +65 6733 3498 Thermnal Ceramics Europe T: +44 (0) 151 334 4030 F: +44 (0) 151 334 1684 North America -Sales Offices Canada T: +1 (905) 335 3414 F: +1 (905) 335 5145 Mexico T: +52 (555) 576 6622 F: +52 (555) 576 3060 United States of America Eastern Region T: +1 (800) 338 9284 F: +1 (866) 785 2764 Western Region T: +1 (866) 785 2738 F: +1 (866) 785 2760 South America -Sales Offices Argentina T: +54 (11) 4373 4439 F: +54 (11) 4372 3331 Brazil T: +55 (21) 2418 1366 F: +55 (21)2418 1205 Chile T: +56 (2) 854 1064 F: +56 (2) 854 1952 Colombia T: +57 (2) 2282935/2282803/2282799 F: +57 (2) 2282935/2282803/23722085 Guatemala T: +50 (2) 4733 295/6 F: +50 (2) 4730 601 Venezuela T: +58 (241) 878 3164 F: +58 (241) 878 6712 Website: www.thermalceramics.com ALION-CAL-TVA-2739-03, Rev. 3 Attachment G, Page 4 of 9 Attachment H -Min-K Email Defining Characteristics of Min-KDaniel, We have a wide range of formulations, but the material you are interested in is about 20%fiber, 65% fumed silica, and 15% TiO2. This is by weight. The material will not break down entirely, but rather it will break into agglomerates if in a very high shear situation.

I don't have the specific gravity data with me, but it is all the same as you would find for those materials in a CRC handbook.

We don't have a lot of data on destructive testing, as our Flexible product, which I think is the material that interests you, doesn't really fail within the applications that it is often times used. The vibration tests are generally what are the most challenging (rather than MOR or something of that nature which tends not to apply), and the mode of failure on that test is associated with the breakage of the textile or threads, rather than the core. There is a theory that I have read on this material, though I don't know if it is of any use to you. However, the thought are that each time an aircraft takes off or lands (time during which vibration is the most extreme, the core essentially breaks apart a little. However, because the bonding mechanism is simply OH- bonds, the core re-bonds during times of low vibration.

This was a considerable benefit our material has over fiber products which will simply break over time, and hence break down.I am out of the office today, but can be reached at 574-596-3694 if you need anything immediately.

Otherwise, I will give you a call next week to discuss any other issues.Thanks, Ken----- Original Message -----From: Wilkens, Daniel J [1]

Sent: Wednesday, September 15, 2004 1:34 PM To: kvannimwegen

@thermalceramics.com

Subject:

RE: Properties of Min-K Ken: My name is Daniel Wilkens, and I am a colleague of Tim's. Thank you for your original email, I was hoping that you could expand on a few points:*

Can you tell me the percentages of SiO2, TiO2, and fiber? This would help us determine an average size for particulates.

Please specify volume percent or mass percent.-* Do you have information on how the insulation breaks down via destruction?

Does it break down to elementary particles, does it break down in agglomerates, etc?*

Do you have the specific gravity, or density, for the individual materials that comprise the Min-K?Calculation No. SD-0023 Page G2 Revision 0-* Finally, any information you can give on general destruction characteristics would be extremely helpful.Thank you very much for the help ALION-CAL-TVA-2739-03, Rev. 3 Attachment G, Page 5 of 9 Daniel Wilkens Alion Science and Technology, ITS Operations 6000 Uptown Blvd. NE, Suite 300 Albuquerque, NM 87110 (505) 872-1089 ext. 114 (voice)(505) 872-0233 (fax)----- Original Message -----From: Sande, Timothy D Sent: Monday, September 13, 2004 2:10 PM To: Wilkens, Daniel J

Subject:

FW: Properties of Min-K----- Original Message -----From: VanNimwegen, Ken [2]

Sent: Wednesday, September 08, 2004 12:23 PM To: Sande, Timothy D

Subject:

RE: Properties of Min-K Tim, Please let me know if we can be of any additional help. We also work closely with some fabricators who are involved in nuclear work if you need any installed systems.Ken----- Original Message -----From: Sande, Timothy D [mailto:tsande@

alionscience.com]

Sent: Wednesday, September 08, 2004 1:15 PM To: VanNimwegen, Ken

Subject:

RE: Properties of Min-K Ken, That information will be helpful. Thank you very much.Tim----- Original Message -----From: VanNimwegen, Ken[mailto:kvannimwegen

@thermalceramics.com]

Sent: Wednesday, September 08, 2004 12:00 PM To: Sande, Timothy D Calculation No. SD-0023 Page G3 Revision 0 ALION-CAL-TVA-2739-03, Rev. 3 Attachment G, Page 6 of 9 Cc: Duchon, Frank; Reisinger, Allen

Subject:

RE: Properties of Min-K Tim, The as-fabricated density of our product varies with thickness and shape, which is why we tend to provide the core density rather than as-fabricated.

With that said, I have attached a TechNote which provides you with the basis weight (mass/area) of our most commonly used flexible products.Several materials are used in our core product including SiO2 particles, which are sized from 0.01-0.015 microns, TiO2 which is sized at less than 5 microns, and fiber products, most of which are between 2.5-10 microns in diameter.You may also be interested to know that we have two specific formulations which contain an additive to allow us to pass NRC 1.36.Regards, Ken Van Nimwegen----- Original Message -----From: Sande, Timothy D[mailto:tsande@

alionscience.com]

Sent: Wednesday, September 01, 2004 3:45 PM To: Min.K@thermalceramics.com

Subject:

Properties of Min-K I'm looking for information on Min-K in order to perform analyses on its use in nuclear power plants. Specifically, I need the as-fabricated density, and the material or particle density and size. Can you provide me with this information or let me know where I can go to get it?Thank you, Tim Sande Assistant Engineer Alion Science and Technology ALION-CAL-TVA-2739-03, Rev. 3 Attachment G, Page 7 of 9 Calculation No. SD-0023 Page F1 Revision 0 Attachment F -Microtherm Email Defining Characteristics of Microtherm

Original Message -----From: Mark Mortimer Sent: Wednesday, September 15, 2004 9:28 AM To: Mark Burton Cc: Geoff Carr; Jeroen Goetschalckx

Subject:

RE: Seeking technical support

Dear Mark,

It sounds as though Daniel is working on a calculation of settling rates for the material if completely dispersed in water.If completely destroyed, Microtherm would revert to the particle sizes of the constituent materials.

Broadly speaking, Microtherm Super G is composed of filaments, fumed silica, and titanium dioxide in proportions of 3%, 58%, and 39%. We usually supply Super G into the nuclear industry but it is worth checking this in case it is Super G hydrophobic, which will float.The filaments are 6 mm long and 6 microns in diameter.

Specific gravity is approx 2.65 g/cc.The titanium dioxide is irregular but broadly spherical, particle size centred around 2.5 micron, specific gravity 4.2 g/cc.The fumed silica is a bit more complex, as it is formed of spherical primary particles fused together into irregular three dimensional branched chain aggregates which are further mechanically entangled into approximately spherical porous agglomerates.

The agglomerates are centred very roughly around 20 microns diameter and have a specific gravity of around 0.06 g/cc (in air). I think for these purposes the agglomerates can be regarded as the fundamental particle, because it takes a great deal of dispersion energy in a high shear mixer and the use of dispersants to break the agglomerates down to aggregates.

Cabot or Degussa are the manufacturers of fumed silica and could probably offer more information if required.

The behaviour of fumed silica in liquids is complex because it tends to form a cross linked gel in many circumstances.

If the Super G is supplied as naked block, it will have a packaged density of 350 kg per cubic meter (0.35 g/cc). If it is supplied as glass cloth covered panel it will have a packaged density of 240 kg per cubic meter (0.24 g/cc).I hope this answers your questions.

Please give me a call if you need any more info.Best regards-Mark " Dr Mark Mortimer Manager, Materials Research Group ALION-CAL-TVA-2739-03, Rev. 3 Attachment G, Page 8 of 9 Calculation No. SD-0023 Page F2 Revision 0 Direct Dial: +44 (0)151 6066211 Business Fax: +44 (0)151 606 6216 e-mail: mmortimer@microtherm.uk.com MICROTHERM INTERNATIONAL LTD., 1 Arrowe Brook Road, Upton, Wirral CH49 1SX, UNITED KINGDOM----- Original Message -----From: Mark Burton Sent: 15 September 2004 14:30 To: Mark Mortimer Cc: Geoff Carr; Jeroen Goetschalckx

Subject:

FW: Seeking technical support Hello Mark Mark can you provide me with the proper response for the questions below from Daniel Wilkens?Particle size of Microtherm if completely destroyed , Packed density, and Particle density. If more information is needed from Daniel let me know .Microtherm will be used in a Nuclear facility in New Mexico.Thanks Mark----- Original Message -----From: Wilkens, Daniel J [3]

Sent: Tuesday, September 14, 2004 10:05 AM To: Sales US

Subject:

Seeking technical support To Whom It May Concern: My name is Daniel Wilkens. I am currently working on a calculation for Shearon Harris Nuclear Power Plant involving debris generation, specifically the destruction of insulation due to a high-energy line break. One of the insulation types at Shearon Harris is Microtherm, inserted as'sheets' into RMI cassettes around the reactor.I am searching for material properties for this product, specifically the following properties:

Packaged density Particle size Particle density In regard to the above, I am using the following definitions:

Packaged density -the density of the product as shipped to customers Particle -the fundamental size if Microtherm insulation is completely destroyed I look forward to your response, thank you for the help.Regards, Daniel Wilkens Alion Science and Technology, ITS Operations ALION-CAL-TVA-2739-03, Rev. 3 Attachment G, Page 9 of 9 Calculation No. SD-0023 Page F3 Revision 0 6000 Uptown Blvd. NE, Suite 300 Albuquerque, NM 87110 (505) 872-1089 ext. 114 (voice)(505) 872-0233 (fax)----- Original Message -----From: Mark Mortimer [4]

Sent: Wednesday, December 08, 2004 12:46 AM To: Wilkens, Daniel J

Subject:

RE: Seeking technical support

Dear Daniel,

The proportions are in wt.%.Best regards-Mark----- Original Message -----From: Wilkens, Daniel J [5]

Sent: 06 December 2004 14:44 To: Mark Mortimer

Subject:

RE: Seeking technical support Mark: I am writing to confirm a small detail regarding the specifications to microtherm you had provided three months ago. When you listed the proportions of filaments, fumed silica, and titanium dioxide (3%, 58%, and 39%), are these specified as wt% or vol%? This will be very helpful to me if it could be cleared up. Thanks again for all of your help.Regards, Daniel Wilkens Alion Science and Technology, ITS Operations 6000 Uptown Blvd. NE, Suite 300 Albuquerque, NM 87110 (505) 872-1089 ext. 114 (voice)(505) 872-0233 (fax)

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation

,,6-E4. N IDocument No: ALION-CAL-TVA-2739-03 Rev:3 Page: H-I of H-i1 ATTACHMENT H -FOAMGLASS/ARMAFLEX This attachment contains the fax from Watts Bar containing the Armaflex and Foamglass design basis information used for this analysis.

AP1R-27-2LW5 08:58 M3u-t tickucEM 4~.751, 7084ý p..02'U M 0 emra'rbýcýJ

'&j TENNES~To .A. RJauston, Chlief,- Nulear 'nsineering-Support MEVALiUiX AUTF&I,,.ATY

'82 1102 002 Branoh, W10C126 C-K,.FfOM' : C. A. Chandley,, Chief,, Mecbanieal

ngineering., SuPport. Branch, W7C126 C-K DATE OCT.9 ' 8211.12.C 04 sUvzcT: WATTS BAR NOCLEAR ePLANT UNITS 1 AND 2 -NARC QUESTIOMS

...." suRvey We, allcnwledge reotJ.ipt of, your- memoranduim dated.May 10, 19$2 (NE) "820510 253) requestlng additional-information on NRC question 212,113. Attached is wB'IE response it, othe request. for a deaiie. insulation survey and questions.

ponoerning.potential sump, soreen by insulation,.

~e (Attachments)

I.L.. Beltz, W7C1k13 C-K.J, #1. Littler W7TC135, Cý-K R. M. Pierce,, 10~4 E9TA-X 'Principl 7--Tripared By: C. I.Mills,. Extension 2.29 k!Z E52298.o5 r 7 flPt y / !..* 4: ~fl~!' Ii~~di ~t'c U~/I~~ flfl I *'t ALION-CAL-TVA-2739-03, Rev. 3 Attachment H, Page 2 of 11 APB'B- 20 0:59 McM~icEM:423 75j 7?064 P 03/11f ATTACHMNT Conf~imatryItem

-Inftorstian Rtequest, Backkround 4 The response (FSAR Amendments 46 and 48 ýto RSB questions ooncerzning 4ump debris (Q212.116) and the Letters referenweddo not provide all the informatfon (per Q212.116)Ineaesaary topertopru a plant rpecitir analytical assessment.

Herein is the detailed insulation survey to oompleta.

this information.

Queotio -212.113 (212.116)

(6a3)4. With regard to the sum tests on- XattB'bar, the:

to the t'oilowing concerns pertaSinin to potentlil sump screen blockage are'required: a, Various types of insulation may be used in the contairnment.

For 6ach type provide the rollowing.Information:

(1) Themanuracturer, brand name, volume and area covered.(2) A brier descrp~tfon ot the ma trial and an estimate ot the tendency.

of th'is material either ýto form. partioles sMall ei-nugh to.pas through the fine sraeen in the sump or eo blook the. oump trash, racks, or sump,,-soreenn,Locatl6n of the material (metal mtirrored, f0am glass, foam'riubb-er, foam iconcreite fibergla~ss

qo.) with' respect 1o, whether a meohanisib exists Coe the material to be transported.b. Provide.-an etimate..

of the. amoint Or debris .that the sump tfl-: screena may~be subjected to during a 16s6-of'-ooolant.

aooPK.1int.

Describe the origin .oV~the debri8 and drsign features "-. the containment sump 66d equipment Ahich wouldOrecludr

+he Ocreene_becoming blOcked.or the +ump plugged by debris, four discussfon should include consIderation of' at least thr ,ollowinq sources of possibir debris: equipMent insulation, ;.lid plug mater1als., reactor cavity-annulus'sand tanks or rnd bags'for hiolojical shieldting; nontainment loose insul" ion, and debris which could be generated hy failure of' non-saf vy rea.ted equipment.

within the.oontainment.

Entry :ot sand >.LuR materials into the containment nump and the possibility, r sand covering the recirculation line.inlets prior to the I- ,tion of reciroulation flow from the cont'iment shoulrl _e specifically, adcnsed'.A ALION-CAL-TVA-2739-03, Rev Attachment H, Page 3of 11 RR27-2~~5 b3. 59 tc~~r MCt1b6EM1 423 751 7084 P.-04'l1i 2 J. A u, isuiston WATTS BAR MUCLEAR PLANT UNITS 1 AND 2 -URC QLUTIONS 2'12.113 -INSULATION SURVEY.-Please provide this information along with:your conolusion regarding the percentage of the soreens whioh would bo expected 'to be blocked -*v partioles or all sizes, including those reaterthan 25O mils.c. With reepeotto the conclusion that debris with a. specific gravity greater than unity wili settle before reaohing:

the 5u'p cover, oonoider the potential flOr low paths whi&ch may direct significant.

'quanitities of debris laden coolant. into the 6ower' -containment -in the vilnity :of the sump and the availability.or lack of sUtf'ioient horizontal.

surfiace a areas or obstructions to propmote aettlings orýholdup or debris prior to reaching the sump.d. Does metal mijror insulation hou.se other materials, fibrous or otherwise whýfich col ecomfi debris if, the -insulat.

on were bloiwn off as a result of d LOCA?e. If the Watts Bar containment contains looseuinsulatIon, inolude examples of how the inslation will. be precluded rrom %reaching the sump, q I F r 4-1 F 4, I.I J~'1 I Responses Manufacturer Mirror InsDulation Divisioh.Diamohd Power Specialty Pittsburgh Corning Corporation Brand Name Mirror Insulation Foamglaar Volume and Area Covw: !d neadto'r, Voosel, Steam:Genera torse ressurizer, Reactor coolant Pumps and .,ing, RKR Piping,%.. Piping, Main Steam, and Feedwater Piping Refrigerant lines and duat to Instrument Room,!I-foot high band around dcntainment Vessei, 80 percent or Toe Condenser piping r U U,, ALION-CAL-TVA-2739-03, Rev. 3 Attachment H, Page 4 of 11

ýFR-ý2?-ý-2005 OB: 59.Pc~cEm~PR27205 8:5 i1cuc~1423ý 751 7064. P. 05/1k~3 J.A. Itaulstofl WATTS BAR~ NUCLEAR PLANTS UN1TTS I ANID 2 -NRC. QUEATIONS 212-113, -IWSULATX tI SuiRv'y RubaiexCoortn Owens /Corning Fiber~gluss.Christiansen Poem, Corpor~ati .on.E. R. Carpenter (Furniaihod by Weo~tinghousp)

Frorty.Sight inaulfttors Incorporated RubaLfx Fiberglas3 POlyurethane Foam Polyurethane Foam Urethane Fo~m Mineral Wool 20 percent of Ioe Condenser piping piping inside air handling units located in upper plenum.area OC.IceCondenser (approxi~mately, I foot, ofpipe per air handliOg unit. Also used for orane wall insulatiot, and vall -insulation, and, sealin g Joints. of, Ua4l panels of Ice Condenser Wall. pAnel insulation betwsen steal.air oooling duota end the. oonoontr o steel containment shell Top deolcinsulation of loe'Condenser insulating ins Ic Tee.Condenser dr-,rs Main nispe penetrations-.Or Vessel'$1 I,~ 1.~~t. ~, I)I-f,.I.11 WI I.14:i ALION-CAL-TVA-2739-03, RT.'3 Attachment H, Page 5 of 11

09:~0 iJCEM 423 751 708z P.~-J. A. Raulaton WATTS BAR NUCLEAR PLANT UNITS 1 AND 2 -NRC QUESTIONS 212.113 -INSULATION SURVEY h(a)(2) and 4(a)(3)Mirror insulatia-is a all-metal refleotive insulation constructed 6f austenetic stainless steel. The metallic reflective insulation -is strong machanioally and composed of sections Whigb are latched together when in place. The seotions will not segment or breakup into small particles.

The sectidons i.ll sink to the bottom "and w ill remain s.ttionary.

Insulation in the vicinity of the pipe break will. be blown or stripped oftF It- is not oonsidered that the sectione would:"be tornapart due"to their strong mechanical construction.

Foamglass Insulation is a rigid insulation composed.ofl sealed- glass', cells. Each cell is'an insulatina air space., Foamglass is all-glas and f is completely inorganic.

The insulation on refrigerant lines, ducts, and piping is covered and banded by'stainless steal jacketing-to minimize or the conditions whereby the insulation could, crumble. The insulation on the containment vessel is covered by. a stainless steel sheath. This, insulation is also located in areas least affected by: postulated pipe breaks (i.a, in upper regiona of the oontainment and outside the crane wall.). In.addition to it. being. completelyjencased as well as being located in areas protected.from the effects of pipe breaks,'this insulation will and cannot enter, theBsump because. of a 8.0 foot minimum water level 4hich exists over the.sump coverplate before recirculation beqgins.Rubate* Insulation is a elexibie closed cell rubber.

This insulation is locat ed' on portions of-the ice oondenser systeT where e it is least affected by. postulated pipe breakb (i.e. uPper p3P\.marea+of the ice condenser).

This insulation is not expected to surdr damage9 from: art primaryý systebi pip~e ..breadk; hoWever', it a should , oe ta h insulation will float and could not enter the sump t- ause tofa 8.0 foot minimum water level whkoh exists over the 6 ump c'-.'rplate bei'ore recirculation begins.ALION-CAL-TVA-2739-03, Rev. 3 Attachment H, Page 6 of 11 RPR-27-2005.

es, oe iMcNucEM 423,751 708,4 P.07/11 5 ,J. A. 'Raulston WATTS BAR INUCLRAR.-PLANT UNITS .I AND 2 -UNRC QUESTIONS 2.12.113 -IMSULAT-IO SURVEY Fiberglass -nsula'tion is. a. glass fiber preformed pipe insulation ,encased in a vapor barrier jacket for the air handling units.: -For the Ice Condenser pe. i- wall insulation, end vall insulation, and for ealing ,the Joints in the i.e condenser wall, the glase fiber Is in blanket form enclosed in polyethylene btagp and oovered by metal panels. The insulation in all oases is behind metal (I.e. inside' housing, or air handling unit 'or' under metal well panels) to proteot._and assure it does.not have, a ..pathway to the Sump., Polyurethane and Urethane Foam Insulation is closed cell urethane:

reain "i foam, TheF polyurethane feam between the air ducts and the oontainment vessel does not have a pathwoy td the sump. The polyurethane form Insulating the 'op deck of the Ice Condenser is. a blaiket between stainless steel sheaths. The assembly rests. on floor grating land is hing ed at the crane wall to form doors that open upon a4 tOCA. iThi s a assembly miai ad its integrity when tested under blowdon *onofitionsi that exceeded the.worst LOCA, The urethane, foam insulatingthe Ice Condenser inlet doors is c6mpletely enclooed, Refer to"FSAR Figure 6.7-17 and 6,7-20. These doors have' been tested. rigorously., Mineral Wool Insula4tion is a refactory fiber block' insulation laminated and bonded by high temperature binders. The insulatidn is between! the.process piping and the penetration sleeve and would not be subjeOt to direct spray" and water from pipe breaks,.4(b)Restraints will prevent pipe-whip

'thereby limiting the .,ijunt ofr insualationthat could. be .blown off to that around tlv ptpe at Lthe -break location', The.- worst case wouldib~e.:a, break locate? immediately under the point at which two sections, or mirror insulati-_, abut in the longitudinal direction of t *he pipe. No more than halr che abutted insulation sec'tion dould be .blown towrdH the- ump..am ALION-CAL-TVA-2739-03, Rev.-T-Attachment H, Page 7 of 11 OFýR-2?ý2005 0-3:'- '.00 423 751, 7B4 P.ýOq/ij 6A. Rauleton WATTS BAR NU1[,EAA PLANTS UNITS" I AND. '2 N BRC QUESTIONS' 212. 113 1- NSULATION SURVYR The mirror inshaltion is oylindr$oal oi the etraight p.ortionS of the primary. system li ng. Over elbows, the, outside surfcea is composed ýof flat seetions in tile shape of rest&ngles.of*

the outside and -inside bends of the: elbow, and in the' shape of-trapezoids on the'elbow sides. The largest, single flat outside, Surface area oft the insulation covering an elbow is 6,808 square feet. In er'Oes seotion, a seotton end has. a parting* surftee area of 1.79 square "feet and, the longest straight length has a.parting' hurface area in the, longitudinal direction of 2,0 square feet.'The, sump isn loated beneath the refueling canal to provide protection frmin high 'ebergy piping- .failureas.

Additionally the area around the sump isenclosed on two esi.des by concrete walls and on -two sides by walls consisting of. structural steel. and 1/4-ineh mesh backed by 1 1/2-inch gCating..

Considering the curvature of 6he,' insulation, over- straight.portions of'the-primary system piping and the angvilarity of the insulation over elbows., .and the quantity of equipment and supports anchored to ýthe containment floor that would prevent movement of settled.Insul'ation sections, the mqaximui possible screened area that could be blocked is very small,. Any :contact between an insulation section and the screen wall would probably be along a line or at a point in the-unikely event.that some of the mirror insulation were to fall against the iiscreen wall. Sinces the Insulation oovering one elbow together with the insulation covering one strailht length of piping is all that could-be affected by a given break, there is only one outer flat. surface of insulation available to contact 'the screen wall. The o0nl other fXqt sur faes. .either are alans longitudinal or transverse parting surfr.es.In the mo1st conservative hypothetieal case, the largeit. f3,W% surfaces area of insulation covering an elbow together with the '.a'eet parting'sur~face of the longest ýtraight nedtion could be as.',_ed to be -against-the screen wall. Thte total area blocked by theev- ;wo sections.

of mirror, insulation would be 8.88 square feet of the n o. screen. area,of. P65i.9 uquare" fee't. Therefore, this small blockt. would, have a

-om_ wold haeahgl.il effect on sump operation.

'I ALION-CAL-TVA-2739-03, Rev. 3 Attachment H, Page 8 of 11 r-PR-27-2M5 09: 01, Jt 423 75j 7084 -p.09/11 J,. A. Raulston WAITS BAR PLANTI.UNITS I 'AND .2- NRC QUIPTIONS:212-.I13-INSULATION SURVEY.'1ia) '4: Mirror insult ton is made entirely of stainless rteela het. materaia and doesenot contain any other materials.

Mirror Insulat o" will not 6egment or break up lnto small particles.

The*Sections witll sink to the bottqm. and remain stationay.

.Fonmklass and Rubatex a"re installed in ai mnner and/or in locations that will.preolude damage fromprimary system pipe breaks; however it should, be-noted that.tha insulation will float and could not enter the sump b'ecause ofra 8`.0 root minimU= water level. Which ex(ats over: the sump cover plate. This Insulatio is located outside.the crane wali.Fiberglass is looated within the housing of the air handlingunits used to cool the ice oandenser.

or is covered 'by meta.1 panels- or sheaths. This protection assures that the insulation, will' not.enter the:,sump."Polyurethane and Urethane is sandwiched between the- teel cooling.ducts and. the containment vessel or is covered by metal panels-or sheaths.This will assure the insulation will not enter the aump.Mineral Wool is located between the sleeves send -the. prooesspi pe .o:he I penetrations.

The spider oonstruotion of the penetration will prvvent the insulatiOn from being pushed from within the penetration.

There should be no turbulence or-direct sprays direoted into tho .enetration cavities.

The penetrations are located outside the ,or- ,e val. This shouid prevent any pasoagaway of the insulation t45 '..ie sump.ALON-CAL-TVA-2739 of03Rv 3 Attachment H, Page 9 of I1I APR-Z?-2005 09:'91 cNcEi4371?8 P.0i M1cNvcEM 42-3 ?51. 71084 P. 10,ýl I SER Supplement No. 2 NlUREG-0847 Supplement N.o. 2!SAFETY EVALUATION REPORT related to the operation of Watts Bar Nuclear Plant Units 1and 2.Docket Nos. 50-390 and 50-391 Tennessee Valley Authority U.S Nuclear Regulatory Commission ALION-CAL-TVA-2739-03, Rev. 3 Attachment H, Page 10 of 11

'PPR-27-20W 89:OtMt1c~.MrNucEMl 423 751 7084 P.11/l-1 6 ENGINEERED SAFETY FEATURES, Supplement 2 6.3 Emergency Core.Cooling System -Page 6-1, Supplement 2 6.3.3 Testing -Page 6-1, Supplement 2 To ensure that debris following a loss-of-coolant accident will not compromise the performance of the emergency core cooling. system by clogging the sump, the staff asked theapplicant-to perform a detailed survey of insulation materials useddwithin the containment.

The app!icant provided-this informationin a letter dared November 2 3, 1982. This surveyconfms the staffs' initial conclusion thbat the Watts Bar design to provide, protection against sump debris: is acceptable.

The reactor system and main steam piping and components are encased in retal reflective insulation that, if dislocated by almajorpipe.

rupture, would.not form small debris particles that would clog the. sump screens. Other materials (foam glass,Rubatex, fiberglass, polyurethane foam, urethane foam, and rnineral wool) areeither enc apsulated in steel or located in areas of, the containment where they would be unaffected by pipe rupture forces.The stiff concludes that the'Watts Bar design regarditg pr'otection against surnp debris is acceptable and this isuea, therefore, is. closed.ALION-CAL-TVA-2739-03, Rev. 3 Attachment H, Page 11 of 11 Watts Bar Reactor Building GSI- 191 Debris Generation Calculation A.L ON Document No: ALION-CAL-TVA-2739-03 I Rev:3 Page: 1-1 of -I I ATTACHMENT I -ICE CONDENSER DEBRIS This attachment contains the Ice Condenser Loose Debris Listing as provided by Watts Bar.

ALION-CAL-TVA-2739-03, Rev. 3 Attachment I, Page 2 of 11 FOREIGN OBJECTS VS BAYS Some Item No.s may fall in more than one category.ICE CONDENSER DEBRIS INDEX Page 72 of 82 ALION-CAL-TVA-2739-03, Rev. 3 Attachment I, Page 3 of 11 Ice Condenser Debris Index BAY BASKET FLOW OTHER LOCATION DESCRIPTION EVALUATION NOTES 1 A6 Bottom of basket A6 Gray duct tape, 2 to 3 inches in length 105 NEW UIC3 1 C5 Bottom of basket C5 Unidentified debris appearing to be metallic.

98 REMOVED U1C4 1 D8 Bottom of basket D8 Cellophane tape 97 REMOVED U1C4 1 F6 103 2nd lattice from bottom in flow Clear plastic sheet 1' x 2' 100 NEW U1C3 passage 1 G2 Bottom of basket G2 Blue tie 2 REMOVED U1C4 1 12 Basket 12 Thermal drill head is larger than the 3 openings on the side of the basket 1 42 Flow passage 42, 6-feet from bottom Undetermined length of grass tie-off rope 92 of baskets 1 138 Flow passage 138, 12-ft up from 12 inch long, black tie-wrap found 93 bottom of baskets 1 151 Outside wall flow passage 151 to 162 Whisk broom dropped to the bottom of the 5 REMOVED U1C3 flow area 1 X End wall and turning vanes -Floor Window Weight 1 1 X Either baskets or floor Seven (7) screws lost 4 1 A6 Near baskets A6 and A7 Artic gear glove 111 NEW U1C4 1 NEAR 15/96 24' down from top near A6 Red shackle pin 127 NEW U1C5 A6 1 3/114 1 2 12' down from top 10 # hammer with long handle 128 NEW U1C5 1 145 12' down from top Electrical tape, 1" x 12" 129 NEW U1C5 1 Near end wall, vertical location Sheetmetal, 11 ga, formed, 3 130 NEW U1C5 unknown pieces approx 1-in x 32-in ea, ASTM A526 or A527 Page 73 of 82 ALION-CAL-TVA-2739-03, Rev. 3 Attachment I, Page 4 of 11 Ice Condenser Debris Index BAY BASKET FLOW OTHER LOCATION DESCRIPTION EVALUATION NOTES 2 G9 153 Flow passage 153 next to basket G9 Broom trapped in lattice frame 7 2 46 Flow passage 46, 6 feet up Stainless steel intermediate deck door ID 91 tag 2 153 6 or 12 foot down from top of lattice Intermediate Brass Deck shim 96 frame 2 FIG X Some where in Bay 2 Ratchet with 1/4-inch socket lossed 6 2 X Lower ice Whisk broom lost 8 3 G6 Bottom of basket G6 Two drop weights 9 3 H4 Bottom of basket H4 Wood splinters 99 4 D3 20' up from bottom 6' of metal banding material 10 4 D4 Basket D4 C-Zone gloves 11 4 E8 Basket E8 C-Zone gloves 12 4 X Row 9 C-Zone gloves 13 4 D4 Near baskets D4 and E4 Ink pen 112 NEW U1C4 5 A2 Flow passage near Basket A2 -6' up Plastic hook (small piece of plastic) from 90 from bottom tube light found 5 C9 X Flow passage next to basket C9; 18- Weight and rope, 14 feet down in flow passage 5 H3 Basket H3 -3' up from bottom Orange plastic (most likely from the bags 89 used to maintain the ice) found -2" sq 5 48/49 Bottom of flow passage 48-49, 12 ft. Piece of air bag (unknown length) found 88 up Page 74 of 82 ALION-CAL-TVA-2739-03, Rev. 3 Attachment I, Page 5 of 11 Ice Condenser Debris Index BAY BASKET FLOW OTHER LOCATION DESCRIPTION EVALUATION NOTES 6 I/H Bottom of basket H/I Yellow plastic found 15 6 X Upper area Putty knife 101 NEW U1C3 7 B7 Outside basket B7, 12 ft. from bottom Orange tie-wrap found 60 7 09 Bottom of basket C9 Small piece of black insulation 16 8 B8 148 20' down from top Flashlight in flow passage 102 NEW U1C3 8 B8 X Flow passage next to basket B8 Safety glasses lodged on a structural 17 member inside .of the flow passage 8 E3 X In upper plenum near E3 1-1/16 inch nut 106 NEW U1C3 8 141 Flow passage 141-6' up from bottom Metal vacuum nozzle found 87 8 X Upper ice baskets; in ice baskets or Screw(s) lost 18 on the floor 8 141 12' up from bottom Rubber shoe cover, yellow 131 NEW U1C5 9 A6 Bottom of basket A6 Metal box cutter 122 NEW U1C4 9 B8 Bottom of basket B8 Wrench is is wedged against the side and 19 bottom 9 B8 Bottom of basket B8 Yellow/Black tape is balled up configuration 20 about the size of a golf ball 9 B8 Bottom of basket B8 Plastic safety glasses found 45 9 C1 X Outside of basket C1 Thin cable, 1/4"x6" long 86 REMOVED U1C3 9 F6 Bottom of basket F6 Gray tape is balled up configuration about 21 REMOVED U1C4 the size of a golf ball Page 75 of 82 ALION-CAL-TVA-2739-03, Rev. 3 Attachment I, Page 6 of 11 Ice Condenser Debris Index BAY BASKET FLOW OTHER LOCATION DESCRIPTION EVALUATION NOTES 9 F6 Bottom of basket F6 Yellow plastic most likely from bags used to 22 maintain the ice in baskets 9 G6 Basket G6 End of stick light in basket 23 9 H1 Near baskets H1 and H2 Open end wrench 113 NEW U1C4 9 H7 bottom of basket H7 1" diameter plug of silicone-like caulk 123 NEW U1C4 10 F3 Basket F3 -45' down from top Drill head is larger than the basket openings 24 10 F5/F6 X Upper plenum in flowpassage near 3/8 inch nut 107 NEW U1C3 F5/F6 10 15 bottom of basket 15 plywood spliter 124 NEW U1C4 10 17 Bottom of basket 17 Brass coupling found 80 10 18 Basket 18 -bottom Duct tape approximately 6 to 8-inches long 81 found balled up 11 B1 Bottom of basket B1 Piece of electrical wire, 1/4"x2" found inside 85 basket 11 15 Bottom of basket 15 2 inch square piece of duct tape found 84 wadded 11 141 Flow passage 141 Light cover from tube light 25 12 D7 125 2nd lattice from bottom Shiny object -unknown 103 NEW U1C3 12 H3 Bottom of basket H3 Red plastic found 26 REMOVED U1C3 13 B1 Bottom of basket B1 Black metal possibly from banding strap 27 found 13 B4 Basket B4- bottom Brass shim found 28 Page 76 of 82 ALION-CAL-TVA-2739-03, Rev. 3 Attachment I, Page 7 of 11 Ice Condenser Debris Index BAY BASKET FLOW OTHER LOCATION DESCRIPTION EVALUATION NOTES 13 C1 bottom of basket C1 rubber like material 125 NEW U 1C4 13 H7 118 Flow passage 118, next to basket H7 FME tieoff (approximately 6-feet long) fell 29 REMOVED U1 C3-6' down from top into the flow passage.13 135 Flow passage 135, 6 feet up 2'-0" piece of air bag found 83 13 X Lost in bay 1/4 -20 x 1" cap screw 114 NEW U1C4 13 19 Near basket 19 9/16" open-end wrench 115 NEW U1C4 13 X Lost in bay Small nut 116 NEW U1C4 14 A7 Bottom of basket A7 Brass shim found 82 14 B3 Basket B3 Yellow plastic (most likely from the bags 30 REMOVED U1C4 that are used to maintain the ice) found.14 H7 116 Flow passages 116/118, next to Strip of red plastic found -1/2" x 4' 31 basket H7, 12 feet up from bottom of basket 14 H8 137 Flow passage 137, next to basket H8; Brass door shim found 32 6 feet down in flow passage 15 F8/F9 1 8/141 12' down from top. Thermal drill head with approximately 10' of 132 NEW U1C5 cable 16 A9 Basket A9; 8 feet down Banding material (carbon steel) found 33 16 F2 Bottom of basket F2 Cellulose based, orange paper found 34 REMOVED U1C4 16 F8 Bottom of basket 1 -inch square plastic UNID name plate .108 REMOVED U1 C4 16 14 Bottom of basket 14 1 inch piece of wood found 79 16 2 Flow passage 2 -between 6' and 12' Two air bags found, assumed to be part of 35 up from bottom larger air bag Page 77 of 82 ALION-CAL-TVA-2739-03, Rev. 3 Attachment I, Page 8 of 11 Ice Condenser Debris Index BAY BASKET FLOW OTHER LOCATION DESCRIPTION EVALUATION NOTES 16 146 Bottom of flow passage 146, 6' up 6 ft. of electrical wire causes a small 78 percentage of blockage 17 D8 Bottom of basket D8 1 inch square plastic sheeting 77 17 El Bottom of basket El red duct tape (in a balled up configuration 36 REMOVED U1C4 the size of a golf ball) found 17 E6 Bottom of basket E6 Brass shim found 38 17 F2 Bottom of basket F2 Red tape (balled up in configuration the size 39 REMOVED U1C4 of a golf ball) found 17 H1 X Between basket H1 and wall Orange plastic (most likely from the bags 40 used to maintain the ice) found 17 13 Bottom of basket 13 Red duct tape found in a balled up 41 configuration the size of a golf ball 17 X Either baskets or floor 4-screw heads from top ring are lost 42 18 A3 Bottom of basket A3 Brass shim found 43 18 A4 Bottom of basket A4 Brass IDD shim found 37 18 B3 Bottom of basket B3 3 in. black plastic strip 76 18 C3 Bottom of basket C3 Black duct tape found in a balled up 44 configuration the size of a golf ball 18 El bottom of basket El duct tape 126 NEW U 1C4 18 F4 Bottom of basket F4 12 in. wadded duct tape found 75 18 F4 Bottom of basket F4 Brass IDD shim in basket 109 NEW U1C3 18 84 Bottom of flow passage 84, 6 ft up Brass shim used in lattice frames found 74 Page 78 of 82 ALION-CAL-TVA-2739-03, Rev. 3 Attachment I, Page 9 of 11 Ice Condenser Debris Index BAY BASKET FLOW OTHER LOCATION DESCRIPTION EVALUATION NOTES 18 139 Bottom of flow passage 139, 9 ft up 5 in. piece of air bag found 73 18 160 12' up from bottom Duct tape, red 133 NEW U1C5 19 D5 Bottom of basket D5 Brass shim found 46 19 D6 Basket D6 Electronic Dosimeter entrained in the ice 94 with the vertical location unknown 20 A5 Bottom of basket A5 Brass shim found 47 20 C5 Bottom of basket C5 Brass shim found 48 20 F1 Bottom of basket F1 Brass shim found 72 20 15 Bottom of basket 15 Brass shim found 49 20 33 Flow passage 33, 6 ft from bottom Cable tie wrap lost 71 20 X Currently entrained in the ice, may be Lanyard, key ring, keys, TLD,badge and 95.in a basket or a flow passage pens may remain as a unit or get separated during a Design Basis event 21 A5 Bottom of basket A5 Brass shim found 70 21 A8 149 2nd lattice down from top Brown plastic sheet -shredded -2" x 2' 104 NEW U1C3 21 D1 Bottom of basket D1 Brass shim found 50 21 F9 By blast wall in basket F9 Cord used to lower the thermal drill down 51 ice basket found 21 4 20 feet down from top Drop weight with 20' of white (cotton?)

rope 110 NEW UlC3 attached Page 79 of 82 ALION-CAL-TVA-2739-03, Rev. 3 Attachment I, Page 10 of 11 Ice Condenser Debris Index BAY BASKET FLOW OTHER LOCATION DESCRIPTION EVALUATION NOTES 21 19 Near basket 19 9/16" open-end wrench 117 NEW U1C4 23 A3 Bottom of Basket A3 Plywood, nut and brass shim found 52 23 A4 Bottom of basket A4 Brass shim found 69 23 H7 Bottom of basket H7 Duct tape found in a balled up configuration 53 REMOVED U1C4 the size of a golf ball 23 15 Bottom of basket 15 2 in. square piece of white plastic film 68 REMOVED U1C4 23 148 12 ft. up from bottom of flow passage 4 in. X 4 in. towel found 67 148 23 X Under the turning vane Putty knife found 54 23 X Lost in bay Two 9/16" nuts 118 NEW U1C4 24 H3 Bottom of basket H3 Orange paper from a bag that contained tie 59 wraps 24 D7 Bottom of basket D7 Duct tape found in a balled up configuration 56 REMOVED U1C4 the size of a golf ball 24 F6 Bottom of basket F6 Stainless Steel banding strip found 57 24 G6 Basket G6 Dark green plywood (2" x 2" x 1/4") and 58 orange plastic bag material (1" x 3")24 H8 Bottom of bsket H8 Clear Plastic from bags used to maintain 61 the ice 24 13 Bottom of basket 13 Brass shim found 62 24 15 Bottom of basket 15 3" spare piece of brass shim found 63 24 97 Flow passage 97 C-Zone Glove found 55 Page 80 of 82 ALION-CAL-TVA-2739-03, Rev. 3 Attachment I, Page 11 of 11 Ice Condenser Debris Index BAY BASKET FLOW OTHER LOCATION DESCRIPTION EVALUATION NOTES 24 118 6' up from bottom in flow passage 118 Black banding strip found 66 REMOVED U1C4 and 119 on the outside of the ice baskets 24 156 Flow passages 156 and 157, 12 feet Air bag found 65 from bottom 24 X Upper ice area, between Crane wall Pry bar lost 64 and Row 1 24 El Near baskets El and E2 One 1 1/8" nut 119 NEW U1C4 24 18 Near baskets and 19 Pencil 120 NEW U1C4 24 Near 16 12' down from top in flow passage Insulated glove, orange 134 NEW U1C5?? X Location unknown Pencil 121 NEW U1C4 Page 81 of 82 Watts Bar Reactor Building GSI- 191 Debris Generation Calculation IDocument No: ALION-CAL-TVA-2739-03 Rev:3 A 0. Page: J-1I of J-5 ATTACHMENT J -DIAMOND POWER RMI This attachment contains the formal letter from Transco stating that from the drawings they sampled, the foil spacing for the Diamond Power RMI is 3 foils per inch.

QA. bwd B38 050504 80.0 T^ TRANSCO PRODUCTS INC.EXECUTIVE OFFICES Fifty Five East Jackson Bld.Suite 2100 Chicago, 111inois 60604-4166 312-427-2818 Facsimile 312-427-4975 BRucz J. ALrPH Vice Peesukut Building Kixellence in Serce. Delhering Energetic Sohltons May 23, 2005 Mr. Heyward R. Rogers 72C(e [-75C)Engineering Manager Tennessee Valley Authority Sequoyah Nuclear Plant Post Office Box 2000 Soddy Daisy, Tennessee 373B4

Dear Mr. Rogers:

In response to your Letter No. 30M518 dated May13, 2005, we have conducted a preliminary review of the Diamond Power design and manufacturing drawings for the reflective metal insulation provided under the Purchase Orders referenced in the letter. While the requested information was not included on the insulation design/assembly drawings, a review of the manufacturing drawings for the following sample component insulation panels established the following information.

SgQuovah Unit 1 Reactor Coolant Pump 2.66" actual insulation thickness with 3 foil liners/inch Pressurizer 4.00" actual insulation thickness with 3 foil liners/inch Based on this sample information, it is expected that the number of liners per inch would not change throughout the four (4) projects listed in your letter.However, confirmation of this expectation will require a concerted effort to retrieve and review all of the insulation manufacturing drawings for the primary components (ie., reactor vessel, reactor coolant pumps, steam generators and pressurizer) and all piping greater than 3" in diameter (i.e., main steam, main feedwater, pressurizer surge, residual heat removal letdown, cold leg accumulator, safety injection, primary system hot/cold logs and crossover legs) for all four plants.If TVA requires confirmation of the manufacturing information for all the insulation provided for the four plants, please advise us accordingly and we will provide a resource and schedule estimate for the data retrieval and review.A CORPORATION OF THE TRANSCO. GROUP ALION-CAL-TVA-2739-03, Rev. 3 Attachment J, Page 2 of 5

.MT. Heyward R. Rogers Engineering Manager Page 2 of 2 Please contact me at 312-427-2818 (x140) if you have any questions or comments concerning this response.Very truly yours, TRANSCO PRODUCTS INC.Vice President RIMS, WTC-K, w/Attachment A CORPORATION OF THE TRANSCO. GROUP ALION-CAL-TVA-2739-03, Rev. 3 Attachment J, Page 3 of 5 Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 H~AY 1 3 ZOO5 Transco Products Incorporated 55 E. Jackson Bouleard, Suite 2100 Chicago, Illinois 60604 Attention:

Mr. Edward Wolbert Gentlemen:

SEQUOYAH AND WATTS BAR NUCLEAR PLANT UNITS I AND 2 -THERMAL INSULATION FOR PIPING AND EQUIPMENT

-CONTRACT NO. 72C61-92750

-LETTER NO. 30M518 REFLECTIVE METAL INSULATION DESIGN INFORMATION REQUIRED TO SUPPORT NRC GENERIC LETTER 2004-02 CONTAINMENT SUMP ANALYSIS -N2M-150 In response to NRC Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors", TVA is currently conducting an analysis of emergency equipment operation in the reactor containment building for the Sequoyah and Watts Bar Nuclear Plants. The analysis involves quantifying the amount of debris generated during certain postulated piping system breaks inside the reactor containment buildings and evaluating the effect of the debris on the ability to recirculate fluid collected in the containment building sump for post event reactor core cooling.In quantifying the amount of debris generated under accident conditions for this analysis, we have reviewed the reflective metal insulation originally supplied by the Diamond Power Specialty Company under the subject contract for primary system equipment and piping systems located inside the reactor containment building.

To support completion of the debris generation calculation, the following information is required to characterize the type and quantity of debris generated by the impact of a high energy pipe break on insulation supplied by Diamond power.1. The number of reflective metal foils per inch of insulation thickness.

2. The average thickness of the reflective metal foil.We have reviewed the documentation file for the subject contract and have not been able to locate this information.

To support the TVA analysis, please provide the information outlined in Items 1 and 2 above for the Diamond Power reflective metal insulation provided for Sequoyah and Watts Bar under the subject contract.ALION-CAL-TVA-2739-03, Rev. 3 Attachment J, Page 4 of 5 A1 3 M Transco Products Incorporated Page 2 The insulation involved in this request was provided under the following Diamond Power Purchase Orders.Purchase Order Plant 590008-R Sequoyah Unit 1 590009-R Watts Bar Unit I 590026-R Sequoyah Unit 2 590027-R Watts Bar Unit 2 Please review the above request and provide a written response.

To support TVA analysis schedules for responding to NRC Generic Letter 2004-02, please provide a response on or before May 20, 2005.Please contact D. M. Lafever at Sequoyah (423-843-8377) if you have any questions or comments regarding this request.Sincerely, f HL R- Rogers, Engineering Manager Sequoyah Engineering and Materials ALION-CAL-TVA-2739-03, Rev. 3 Attachment J, Page 5 of 5 Watts Bar Reactor Building GSI- 191 Debris Generation Calculation 0 N Document No: ALION-CAL-TVA-2739-03' Rev:3 Page: K-I of K-3 ATTACHMENT K -MAIN STEAM AND FEEDWATER BREAKS This attachment contains the formal letter from Watts Bar discussing Main Steam and Feedwater breaks and the plant licensing basis.

T2'5 050526 050 May 26, 2005 Westinghouse Electric Corporation Post Office Box 355 Pittsburgh, PA 15230 Attention:

Krish M. Rajan WATTS BAR NUCLEAR PLANT (WBN)NUCLEAR STEAM SUPPLY SYSTEMS (NSSS)CONTRACT-00026863 LETTER NUMBER W-7850

Subject:

WAITS BAR NUCLEAR PLANT UNIT 1 -CONTRACT WORK AUTHORIZATION NO. WESTINGHOUSE-WBN-2005-008-GSI 191 -CONTAINMENT BUILDING SUMP MULTIDIMENSIONAL FLOW MODEL, NRC GENERIC SAFETY ISSUE GSI-1 91,"ASSESSMENT OF DEBRIS ACCUMULATION ON PWR SUMP PERFORMANCE" Watts Bar Nuclear Plant's licensing basis is such that a break is not postulated to occur in Main Steam System or Feedwater System lines at the locations where guardpipes are provided when penetrating the crane wall, containment vessel and shield wall. Section 3.6 of the FSAR discusses the analysis methodology and postulated break locations and is analyzed in accordance with NUREG-0800 Section 3.6, Branch Technical Position MEB 3-1. Therefore, a break inside the guardpipe for the Main Steam System piping and Feedwater System piping should not be used to characterize the event for which potential sump blockage could occur.Watts Bar Nuclear Plant feels it prudent to consider a sensitivity analysis for a Main Steam Line Break outside of the guardpipe.

ALION-CAL-TVA-2739-03, Rev. 3 Attachment K, Page 2 of 3 Krish Rajan Page 2 May 26, 2005 TVA will provide to the NRC the justification for taking an exception to a break in the Main Steam System and Feedwater System lines where protected by guardpipes between the crane wall and shield wall.Questions may be directed to F.A. Koontz at x1 261.Sincerely, W. M. Justice Acting Site Engineering Manager EQB 2A-WBN cc: D. M. Lafever, OPS 3C-SQN F. A. Koontz Jr., EQB 2A-WBN C. M. Ledbetter, EQB 2N-WBN L. L. McCormick, EQB 2N-WBN R. H. Bryan, Jr., LP 4J-C J. S. Robertson, EQB 2N-WBN C. R. Allen, EQB 2N-WBN EDMS, WT CA-K ALION-CAL-TVA-2739-03, Rev. 3 Attachment K, Page 3 of 3 Watts Bar Reactor Building GSI- 191 Debris Generation Calculation Document No: ALION-CAL-TVA-2739-03 Rev:3 Page: L-1 of L-3 ATTACHMENT L -COATINGS This attachment contains a clarification email from Jon Cavallo, the individual who performed the Enercon Coatings walkdown for Watts Bar.

Page 1 of 2 Tezak, Joe From: JRCPE@aol.com Sent: Monday, February 07, 2005 8:11 AM To: Tezak, Joe

Subject:

Re: Watts BarCoatings...

Joe: Here's what I've got. The info below is based on TVA Drawing 46W466-1 Rev. 23 and TVA General Construction Specification G-55 (various revisions).

1. The coatings on the steel support structures All steel was shop or field primed with Carboline Carbo Zinc 11, 2.5 -5.0 mils DFT. The entire liner plate, and all steel to a dado height of 6' from the lower containment floor were topcoated with Carboline Phenoline 305 4.0-6.0 mils DFT. The Upper Containment Dome was left untopcoated (primer only).2. The coatings on the concrete inside the crane wall Concrete floors: Carboline 295 Surfacer 40-60 mils DFT Carboline 305 intermediate coat 4.0-6.0 mils DFT Carboline 305 topcoat 4.0-6.0 mils DFT Concrete Walls up 6' dado height from the floor: Same system as floors 3. The coatings under the insulation on the crossover leg and main steam lines (if any)I can't find any indication that any coating was applied to these surfaces.4. The coatings on the RCPs According to TVA Nonconformance Report 8633 dated 7/1/87, the RCP motors were coated by Westinghouse with and unqualified system: Ameron Dimetcoat 2 Inorganic Zinc Primer Ameron Amercoat 66 Epoxy Phenolic Topcoat No DFT's were given, but you can assume the primer at 2.5-5.0 mils and the topcoat at 4-6 mils.5. Specifications for the 3M-M20C insulation that they say runs on conduit in loops 1, 2, and 4 Not in my rice bowl -ask Enercon Hope this helps.Jon Jon R. Cavallo, PE Vice President Corrosion Control Consultants and Labs, Inc.Portsmouth, NH (603) 431-1919 ALION-CAL-TVA-2739-03, Rev. 3 Attachment L, Page 2 of 3 5/24/2006 Page 2 of 2 (603) 431-2540 facsimile (603) 767-8650 cell ALION-CAL-TVA-2739-03, Rev. 3 Attachment L, Page 3 of 3 5/24/2006 Watts Bar Reactor Building GSI- 191 Debris Generation Calculation AL 0 N Document No: ALION-CAL-TVA-2739-03 Rev:3 Page: M-1 of M-2 sc.tT.AiCHMDENT umeCntENT RESOLUTI ATTACHMENT M -COMMENT RESOLUTION Comment Resolution Rev.3 Comment Calc. Section Comment Proposed Resolution

1. Appendix 1 -Item The Post Installation Design Package has progressed to EG -Revised per TVA LetterW-8081 258 the point since letter W-8078 that the actual volume of Item 258 will be 0.64 ft^3 rather than 0.87. I will send a follow up W-letter to back up this change. This change will probably ripple throughout the calc. So I don't have a problem with the calc stating that the 0.87 ftA3 value will be retained for conservatism (or something like that). -Steve Robertson 2. Appendix 1 -Item In the Comments Column, insert "W-8078" between the EG -Complied 307 words "Letter" and "dated"- Steve Robertson 3. Page 12 Watts Bar survey was completed on 09/06. Ref W Letter EG -Complied LTR-CSA-06-74.

total latent debris load was 69.2 lb -Cindy Maples 4. Page 23 Watts Bar survey was completed on 09/06. Ref W Letter EG -Complied LTR-CSA-06-74.

total latent debris load was 69.2 Ib-Cindy Maples 5. Page 57, 6th bullet Revise to the following:

EG -Complied The destruction pressure of 2.4 psi and the corresponding ZOI of 28.6D are likely overly conservative for the Min-K with no additional banding in Watts Bar. These ZOI values are for unjacketed Min-K and the installed Min-K at Watts Bar is jacketed in the same jacketing as the RMI.However, the SER instructs to use this value if no test data is available for the plant-specific jacketing.

Jet impingement testing has been conducted on the Watts Bar Min-K configuration with additional banding which shows no insulation destruction at distances beyond 10.0D. -Cindy Maples 6. Page 57, 7th bullet Delete. -Cindy Maples EG -Complied 7. Page 60: Reference Westinghouse letter LTR-CSA-06-74.

EG -Complied ALION-CAL-TVA-2739-03, Rev. 3 Attachment M, Page 2 of 2 Watts Bar Reactor Building GSI-191 Debris Generation Calculation Document No: ALION-CAL-TVA-2739-03 Rev:3 Page: N-I of N-3 ATTACHMENT N -REVIEW CHECKLIST This attachment contains Alion QA Form 3.4.2 -Design Calculations and Analysis Review Checklist.

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ATTACHMENT 2

U k Automated Engineering Calculation Package Page 1 of 107 Calculation Number: PCI-5464-S01 Calculation Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Client: Performance Contracting Inc. Station: Watts Bar Project Number: PCI-5464 Unit(s): I Project Title: Watts Bar Strainer Qualification Safety Related Yes 1 No --Revision Affected Pages Revision Description Approval Signature

/ Signature

/ Initials of Date Preparers

& Reviewers 0 All Initial Issue Curtis J. Warchol Curtis J. Warchol 05/18/2006 (CJW)Scott T. Nelson (STN)1 1-5, 10, 13, Revised to incorporate as-built drawings Curtis J. Warchol Curtis J. Warchol 17, 19, 21, 17- and to incorporate additional client 08/08/2006 (CJW)29, 37, 38, 50, comments 53, 57, 76, 83, Scott T. Nelson 87-94, 97, (STN)100-107 2 1-4, 17, 22, 28, Revised to incorporate unbalanced , ( Jaaxf / I 29, 33, 35, 39, pressure loads on the top of the modules. " 49, 63-64, 94, This revision resolves AES CAR 06-006 Curtis J. Warchol Curtis J. Warchol 100-105 08/25/2006 (CJW)Attach. A & B Kishore D. Patel (KDP)Form 3.1-10 Rev. 0 UAutomated Engineering Calculation Package Page 2 of 107 z k Services Corp.REVIEWER'S CHECKLIST FOR DESIGN CALCULATIONS SHEET 1 of 2 STATION: Watts Bar NUCLEAR SAFETY RELATED: YES 0 NO -'PROJECT NO: PCI-5464 CLIENT: Performance Contracting Inc.CALCULATION TITLE: Structural Evaluation of Advanced Design Containment Building Sump Strainers CALC. NO: PCI-5464-SO1 CALC. REV. NO: .2 INDICATE THE DESIGN INPUT DOCUMENTS USED: TYPE OF DOCUMENT DOCUMENT ID, REV AND/OR YES N/A COMMENT DATE 1. General Design Basis 3,4,5,9,21,22,24,25,31,33,34 X 2. System Description X 3. Design information package 18, 27, 28 X from related equipment vendor 4. Electrical Discipline Input X 5. Mechanical Discipline Input X 6. Control Systems Discipline X Input 7. Structural Discipline Input 7,8,12,13,15,16,17,19,20,26,32,35 X 8. Specifications 1, 2, 29, 30 X 9. Vendor Drawings 6 X 10. Design Standards X 11. Client Standards x 12. Checked Calculations 14, 23 X 13. Other (specify) 10, 11 (AES QA Files) X PREPARER'S SIGNATURE: (.J 4 DATE: 08/25/2006 CurtisS. Warchol REVIEWER'S SIGNATURE:

/ DATE: 08/25/2006 Kishore D. Patel APPROVER'S SIGNATURE:

fA -CriJ W LaoLA4Y 9 DATE: 08/25/2006 CurtisF .Warchol Form 3.1-4 Rev. 3 U~ki REVIEWER'S CHECKLIST FOR DESIGN CALCULATIONS SHEET 2 of 2 PROJECT NO: PCI-5464 CALC. NO: PCI-5464-S01, Revision 2 REVIEWER TO COMPLETE THE FOLLOWING ITEMS: YES INO N/A COMMENT I. Has the purpose of the calculation been clearly stated?2.. Have the applicable codes, standards and regulatory requirements been: A. Properly Identified?

B. Properly Applied?3. Were the inputs correctly selected and used?4. A. Was Design Input Log used?B. If 4A is No, provide Manager's signature in Comment column to signify approval of Design Input Documents used in the calculation.

5. Are necessary assumptions adequately stated?6. Are the assumptions reasonable?

7. Was the calculation methodology appropriate?

-8. Are symbols and abbreviations adequately identified?

9. Are the calculations:

A. Neat?B. Legible?C. Easy to follow?D. Presented in logical order?E. Prepared in proper format?10. Is the output reasonable compared to the inputs?11. If a computer program was used: A. Is the program listed on the ASL and has the SRN been reviewed for any program use limitations?

B. Have existing user notices and/or error reports for the production version been reviewed as appropriate?

C. Were codes properly verified?D. Were they appropriate for the application?

E. Were they correctly used: F. Was data input correct?G. Is the computer program and revision identified?

XI I I X X x x:L I_ _ _ _ _ _X Form 3.1-4 Rev. 3 Form 3.1-4 Rev. 3 U Automated Engineering CALCULATION SHEET Page: 4 of 107 , Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes [I] No D Date: 08/25/06 TABLE OF CONTENTS 1.0 Purpose/Objective

..........................................................

5 2.0 Methodology

..............................................................

5 3.0 Acceptance Criteria .......................

....................................................................

8 4 .0 A ss u m p tio n s ................................................................................................................................................

13 5.0 D efinitions and D esign Input .......................................................................................................................

13 5 .1 M ate ria l P ro pe rtie s .........................................................................................................................

13 5.2 Strainer Geometry and Dimensions

........................................................................................

15 6 .0 C a lc u la tio n s ................................................................................................................................................

2 1 6 .1 W e ig ht C a lcu latio n s .......................................................................................................................

2 1 6 .2 S tra in e r L o a d s ...............................................................................................................................

2 9 6.3 Calculation of Strainer Surface Area ........................................................................................

32 6 .4 G T S T R U D L M odel .........................................................................................................................

33 6 .5 G T S T R U D L R esults ......................................................................................................................

63 6 .6 D isk P ressure Load s ......................................................................................................................

6 5 6.7 Perforated Plate Evaluation

....................................................................................................

69 6.8 W ire Stiffener Evaluation

.........................................................................................................

84 6.9 Core Tube End Cover Evaluation

...........................................................................................

85 6 .10 W e ld E va lu atio ns ...........................................................................................................................

9 2 6.11 Evaluation of Local Stresses in Core Tube at Connection to Radial Stiffener

.........................

95 6 .12 R ive t E v a lu a tio n .............................................................................................................................

9 5 6 .13 C onnection B olt Evaluation

........................................................................................................

100 7 .0 R esults and C onclusions

.........................................................................................................................

103 8 .0 R e fe re n ce s ................................................................................................................................................

10 5 Attachm ent A -G TSTR U D L Input File ...............................................................................................................

1 -23 Attachment B -GTSTRUDL Output File (Run Date: Aug 24, 2006 14:58:32)

.................................................

1 -680 Attachment C -GTSTRUDL Joint Number and Member Number Plots ..........................................................

1 -9 Attachment D -ANSYS Output File (Run Date: 12/23/2005 11:31:50)

...........................................................

1 -575 Attachment E -Testing of Blind Rivets (Reference

[18]) ...............................................................................

1 -5 Attachment F -Perf Plate Thickness Data from Hendricks Book (Reference

[28]) .............................................

1 -1 Attachment G -Vendor Data from Cross Bracing Cable Vendor (Reference

[27]) .........................................

1 -4

< / l Automated Engineering CALCULATION SHEET Page: 5 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes EW No EL Date: 08/25/06 1.0 PURPOSE/OBJECTIVE The purpose of this calculation is to qualify the Performance Contracting Inc. (PCI) Suction Strainers to be installed in Tennessee Valley Authority Watts Bar Nuclear Plant Unit 1. This calculation evaluates, by analysis, the strainer modules. The supporting structures (i.e., plenum) associated with the new strainers are evaluated in a separate calculation.

2.0 METHODOLOGY

The evaluations are performed using a combination of manual calculations and finite element analyses using the GTSTRUDL Computer Program, and the ANSYS Computer Program. The evaluations follow the requirements of the TVA Design Specification for Sequoyah Nuclear Plant Unit 1 & 2 and Watts Bar Nuclear Plant Unit 1 for Advance Design Containment Building.Sump Strainers, Specification No.SQN/WBN-DS-2005-063-001, Revision 00 (Reference

[1]) as supplemented by References

[2] and [29].Seismic Loads The strainers will be located in the space directly above and surrounding the existing sump pit at floor Elevation 702' -9 3/8" of the Containment Building.

The response spectrum required per Reference

[1] is for the 703' elevation of the Reactor Building Interior Concrete.According to the Design Specification (Reference

[1]), the strainers and their supporting elements are required to meet the seismic analysis criteria contained in Appendix D to the Design Specification.

The strainer modules are analyzed using the response spectra method using GTSTRUDL Version 25 software.The strainers are considered "passive equipment" and per Reference

[2], the design should be based on seismic response spectra generated with 2% damping for the Operating Basis Earthquake (OBE) and 3%damping for the Safe Shutdown Earthquake (SSE). These are conservative damping values for bolted steel structures.

The strainer assemblies are excited in one horizontal and one vertical direction.

Since the strainer design is symmetrical, only one horizontal worst case excitation is required.

The worst case response would be identical in the other horizontal direction.

The enveloped response spectra from the E-W or N-S direction is used, and is applied in the worst case direction for the strainer, which is considered to be parallel with the edges of the strainer disks. The results from the horizontal and vertical seismic cases are combined by absolute summation.

The modal combination is performed by the statistical method (SRSS combination) as per Appendix D of the TVA Design Specification (Reference

[1]). The seismic stresses of closely spaced modes (within 10%) are combined by SRSS. Therefore, the TPM (Ten Percent Method) of GTSTRUDL is used for the modal combination.

The cutoff frequency is taken at approximately 33 Hz. Zero Period Acceleration (ZPA) residual mass effects for frequencies above 33 hz are considered and combined with the response spectra modal results by ABS.

_ I Automated Engineering CALCULATION SHEET Page: 6 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 Operating Loads Operating loads are comprised of weight and pressure loads. The weight of the strainer includes the weight of the strainer self weight and the weight of the debris which accumulates on the strainer.

The debris weight is taken from Reference

[23].The pressure load acting on the strainer is the differential pressure across the strainer perforated plates in the operating condition.

Conservatively, this is taken as the hydrostatic pressure associated with the maximum allowed head loss through the debris covered strainers as defined in Section 6.2.1.Thermal expansion loads are considered negligible.

The strainers themselves are free to expand in the vertical direction without constraint.

In the lateral direction, the only constraint is at the bottom of the bottom module.Since the modules are attached to a stainless steel plenum, the thermal expansion of the plenum and the strainers should be about equal resulting in negligible thermal stresses on the strainer modules. The design and operating temperatures for the strainers are defined in Section 5.1.Software MathCad software is used to generate the calculations.

All MathCad calculations are independently verified for accuracy and correctness as if they were manually generated.

ANSYS is used for the analysis of the inner gap plate. ANSYS Version 5.7.1 is fully verified with no restrictions or limitations (Reference

[11]). GTSTRUDL Version 25 is used in the seismic response spectra analysis of the strainer modules. GTSTRUDL Version 25.0 is verified and validated under the AES QA program as documents in the AES validation and maintenance file (Reference

[10]). The validation of GTSTRUDL was a partial validation and only validated certain commands.These commands are listed in the validation report. The GTSTRUDL runs utilize several commands outside the scope of this validation.

A list of these commands, and their alternate validation method used for this particular-application, is provided below: Command Validation Method GENERATE REPEAT JOINT TIES SLAVE RELEASES CHANGES DELETIONS ADDITIONS ACTIVE The GENERATE and REPEAT commands are used to automatically generate member nodes and incidences.

These generated items for these models are verified manually.The JOINT TIES and SLAVE RELEASES commands are used in conjunction with MEMBER TEMPERATURE LOADS to account for the preload on the tension rods.The commands also constrain the pipe spacers and tension rods to move together in certain degrees of freedom. Their use is acceptable because the nodal displacements are manually compared for these nodes to confirm the command is working as planned.These commands simply control howthe program reads and processes upcoming commands.

It is easily verifiable by reviewing the computer output to ensure the results are as expected.

U Automated Engineering CALCULATION SHEET Page: 7 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Caic. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 Command Validation Method MEMBER TEMPERATURE LOADS DEFINE GROUP MEMBER ADDED INERTIA PIPE This command applies a specified temperature increase/decrease to a given member. This command is used as a simple way to generate preload in the rods.Its use is acceptable because the preloads produced by this load are verified manually.This command groups members and/or joints together for easier specification of member properties and load placements.

This command is verified by checking manually that the cross sections and loads are applied properly to each member.This command is used to apply the mass of the certain strainer components not directly included in the model on to members that would carry their mass for a certain direction of seismic response.

This command was verified manually by listing the dynamic mass summary and comparing the total dynamic mass in each direction to the calculated total mass.PIPE is a command used to specify the cross section of the core tube. It is necessary to use this command rather than referencing a pipe cross section from a table because the diameter and thickness are unique to the strainer and are not available in the provided tables. Because GTSTRUDL uses only the section properties when code checking, the properties are printed out for selected members defined by this command and those properties are verified manually.These are predefined GTSTRUDL tables that contain steel cross sections for rectangular and round shapes. The members that are defined by these tables are subjected to loadings and then code checked in GTSTRUDL.

These tables are verified in the same fashion as for the PIPE command listed above. In addition any code checks performed by GTSTRUDL for these sections are manually verified.TABLE 'RBAR'TABLE 'BARS'TABLE 'ROUND'TABLE 'MYCHAN'The limitations and program error reports for GTSTRUDL Version 25 (Reference

[10]) were reviewed for applicability to the GTSTRUDL runs made for this calculation.

The limitations for the 78AISC Code check were found not to be applicable for this calculation (none of the components are subjected to significant torsion, therefore warping torsion stresses would be negligible, and the other limitations deal primarily with structural angle shapes which are not included in this model). Also, steel cross sections that are not available in the GTSTRUDL cross section libraries are created for the face disk edge channels, the external stiffeners, the stiffener collar, the cross braces, and the ends of the external stiffeners where the stiffeners are welded to the cross braces. These cross sections were verified by outputting the computed properties of the cross sections and checking these values manually.

T Page: 8 of 107 Calc. No.: PCI-5464-SO1 I H Ianto Dcrfrn P_ rnnfr + th, Tn, Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 3.0 ACCEPTANCE CRITERIA The strainer components shall meet the requirements of the codes, standards and regulations listed in Section 3.1 of TVA Design Specification SQN/WBN-DS-2005-063-001, (Reference

[1]). Section 3.1 of the Design Specification states that the equipment shall be designed in accordance with the AISC 7th Edition (Reference

[9]), therefore the acceptance criteria will primarily be in accordance with this code. In circumstances where the AISC Code does not provide adequate guidance for a particular component, other codes or standards are used for guidance.

These alternate codes are discussed briefly below.The AISC Code does not provide any design guidelines for perforated plate. Therefore, the equations from Appendix A, Article A-8000 of the ASME B&PV Code,Section III, 1977 Edition (Reference

[3]) are used to calculate, the perforated plate stresses.

The acceptance criteria is also based on this code. In addition, the AISC Code does not specifically cover stainless steel materials.

Since the strainers are fabricated entirely from stainless steel, the ANSI/AISC N690-1994, "Specification forthe Design, Fabrication, and Erection of Steel Safety Related Structures for Nuclear Facilities", Reference

[21 ] is used to supplement the AISC in any areas related specifically to the structural qualification of stainless steel. Note that only the basic acceptance criteria (allowable stresses) are used from the ASME Code and load combinations and allowable stress factors for higher service level loads are not used.The strainer also has several components made from thin gage sheet steel, and cold formed stainless sheet steel. Therefore, SEI/ASCE 8-02, "Specification forthe Design of Cold-Formed Stainless Steel Structural Members", (Reference

[22]) is used for certain components where rules specific to thin gage and cold form stainless steel should be applicable.

The rules for Allowable Stress Design (ASD) as specified in Appendix D of this code are used. This is further supplemented by the AISI Code (Reference

[5]) where the ASCE Code is lacking specific guidance.

Finally guidance is also taken from AWS D1.6, "Structural Welding Code -Stainless Steel", (Reference

[25]) as it relates to the qualification of stainless steel welds. Detailed acceptance criteria for each type of strainer component is provided in the sections below.

_ l Automated Engineering Services Corp I Page: 9 of 107 Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol CaIc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No EI Date: 08/25/06 Load Combinations The applicable load combinations are taken from the Appendix E of the Design Specification (Reference

[1])as supplemented by Reference

[30]. The primary governing code for the strainers is AISC 7th Edition. As per Appendix E of the Design Specification (Reference

[1]) the structural analysis of the strainers, supports and associated equipment shall considered the following design basis loads.1. DW -Dead Weight Loads and forces.2., TOL -Thermal Effect Loads during normal operation (loads imposed by normal operating temperatures, conservatively taken at 140 degrees F per Reference

[30]).3. OBE- Seismic Loads generated by the operating basis earthquake.

4. SSE -Seismic Loads generated by the safe shutdown earthquake.

5. TAL -Thermal Effect Loads during accident operation (loads imposed by accident operating temperatures, taken as the maximum water temperature of 190 degrees F).6. JIL -Jet Impingement equivalent static load (if applicable) (JIL = 0 for WBN).7. DIL -Debris Impact equivalent static load (if applicable) (DIL = 0 for WBN).8. DP -Differential pressure across perforated plates and other pressure boundaries.

9. DEB -Debris weight.The required load combinations are defined in Reference

[30] as: Load Condition* Load Combination 1* Load Combination 2 Load Combination 3 Load Combination 4 Load Combination 5* Load Combination 6 Combination DW + DEB + DP DW + OBE DW + TOL + OBE DW + TOL + SSE DW + DP + DEB + TAL DW + JIL + DIL + SSE Allowable 1.0S 1.0S 1.5S 1.6S 1.6S 1.6S Notes 1,4, 5, 7 Notes 1, 6, 7 Notes 1, 6, 7 Notes 1,6, 7 Notes 1,4, 5, 6, 7 Notes 1, 2, 3, 6, 7* Per Note 3, JIL and DIL are not applicable.

Thermal loads, TOL and TAL, are negligible for the strainers as described in Section 2.0. Therefore, only Load Combinations 1, 2, and 6 require detailed evaluation, and Load Combination 6 reduces simply to DW + SSE.

Automated Engineering CALCULATION SHEET Page: 10 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes No D Date: 08/25/06 Notes 1. For structural steel, the "S" value is the required section strength based on the elastic design methods and allowable stresses defined in Part 1 of the AISC specification, Seventh Edition, referenced in Section 3.0 of the Design Specification (Reference

[1]). The 33 percent increase in the allowable stresses for steel due to seismic or wind loadings permitted by the AISC standard shall not be applied to this evaluation.

When altemate codes are used for guidance, the "S" value is defined consistently as described above, except that the standard allowable stresses are taken from these other codes. Additional detail for each type of component is provided below.For perforated plates, the "S" value is the allowable stress from the ASME Section III Boiler and Pressure Vessel Code,Section III, 1989 Edition including Appendix A, Article A-8000 provisions for calculating perforated plate stresses.For concrete anchor bolt, the tensile and shear forces shall not exceed the allowable loads for the selected anchor bolts in TVA DS-C1.7.1 (Reference

[5]). TVA concurrence with anchor bolt selection is required.

Thermal stresses on anchor bolts shall be considered and minimized by the design.2. The AISC allowable stresses for Load Combination 6 shall not exceed the following limits (excluding perforated plate)0.9x SY for Tension or Bending Stress (0.9x Sy) / (3.0)0.5 for Shear Stress 0.9x Scb for Compression Stress where Sy =minimum specified yield strength of the material, and Scb = the critical buckling compressive stress calculated by the AISC equations without the appropriate factor of safety.3. The Jet impingement load (JIL) and debris impact load (DIL) are negligible for the final strainerdesign.

4. The differential pressure (DP) shall be the larger of 3.5 feet of water or the design basis head loss as determined by the evaluation performed in response to Section 7.4 of the Specification (Reference

[1]).5. Debris weight shall be considered for Load Combination 1 and 5. The debris weight on the strainer shall be the larger of 25 pounds per square foot applied to the total stariner/flow plenum horizontal footprint, or the maximum calculated debris weight transported to the strainer under design basis conditions.

6. Per Reference

[2] and [30], the design and licensing basis of the Watts Bar containment sump intake structures does not require the consideration of- a seismic event during recovery from a design basis accident.

As the containment sump strainers will only be underwater during the recovery from a design basis event, seismic / structural qualification of the advanced strainers in the flooded condition is beyond the current design and licensing basis of the plant. As such, the hydrodynamic effects of a seismic event which occurs when the strainers are underwater need not be included in the structural evaluation.

I Page: 11 of 107 Caic. No.: PCI-5464-S01 TRpvidinn.

9 C liont. Psrfnrrnonr'c' rnntrartinn Tnr Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Cale. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No Dl Date: 08/25/06 7. Per Reference

[21], because stainless steel does not display a single, well defined modulus of elasticity, the allowable compression stress equations from the AISC are not applicable for stainless steels.Therefore, the allowable compression stress will be based on the lower allowables from Reference

[21] as opposed to those provided in the AISC Code (Reference

[9]). Per Q1.5.9.2 of Reference

[21], the allowable stresses for tension, shear, bending and bearing for stainless steel can be taken as the same allowables provided for carbon steel, therefore the AISC 7th Edition will be used for allowables for these types of stresses.GTSTRUDL Code Check Most support components are qualified using the GTSTRUDL code check features.

The GTSTRUDL AISC 7th Edition Code check is not QA verified in AES's QA program, therefore the AISC 8th Edition Code check is used (78AISC).

A code reconciliation was performed between the 7th and 8th editions to identify any differences that could affect the results. Although there are differences between the two codes, by reviewing the code provisions checked with regards to the types of members in the model (channels, rods, and bars), there are no significant differences between the AISC 7th Edition requirements and the evaluation performed by GTSTRUDL using the AISC 8th Edition. Therefore, the use of the 8th Edition Code check feature of GTSTRUDL is acceptable for this application with the exception of the allowable compression stress as described above. The effective buckling length factor, K, will be manually adjusted to account for the lower compression stress allowable.

See Section 6.5.8 for additional discussion.

The parameter "Code Tolerance" is used in GTSTRUDL to allow for the higher stresses associated with Load Combination

6. This parameter is used to only flag members with an interaction ratio higher than a certain threshold as a failing member. In this way, if a particular member is only 10% overstressed from standard AISC allowables, it is not flagged as a failing member if the Code Tolerance is higher the 0.10. Based on the allowable stressed defined above for Load Combination

6, the Code Tolerance is calculated as follows: mlr., 0.9 Sy 0.9 Sy 0.9 CT := min 1.6, ,- CT = 0.30 0.66.Sy'-,/-.O.4.Sy' 12 23 where 0.66 Sy is taken as the worst case bending stress allowable for the non-rectangluar members, and 12/23 is taken as the standard code factor of safety against buckling.

For rectangular members, the code tolerance for weak axis bending is taken as: 0.9 CTrect:= 0. 1 0.75 CTrect = 0.20 I Page: 12 of 107 Calc. No.: PCI-5464-SO1 R1Avicin.

I 9"]aint ID -rfnrrn- ac, Inrat -I-f;n -Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Caic. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes W No D Date: 08/25/06 Edge Channels The edge channel and the attached perforated plate work as a combined section to resist bending loads. The effective width of the perforated plate that acts in combination with the edge channel is based on Section 2.3 of the ASCE Standard for Cold-Formed Stainless Steel Structural Members (Reference

[22]), which provides design guidelines for very thin members such as the perforated plate. The effective width of the plate is limited by the width to thickness ratios such that local buckling of the plate will not occur for the compression face. The minimum spacing and edge distance required for the rivets is based on the AISI (Reference

[51)requirements for screw spacing.Strainer Perforated Plates For the perforated plates, the AISC Code does not provide any design guidelines.

Therefore, the equations from Appendix A, Article A-8000 of the ASME B&PV Code,Section III, 1977 Edition (Reference

[3]) are used to calculate the perforated plate stresses.

Note that Article A-8000 refers to Subsection NB for allowable stresses, which are defined in terms of stress intensity limits, Sm. Conservatively, stress limits are based on the standard allowable stress, S, as opposed to Sm. NB-3220 provides stress limits for the primary membrane, and primary membrane plus bending. Based on this section, and as allowed by Reference

[29], the allowable stresses for the perforated plate are as follows: Load Condition Stress Type Allowable Stress Normal/Upset Primary Membrane Stress Intensity 1.0S Normal/Upset Primary Local Membrane + Bending Stress Intensity 1.5S Welds Welds for strainer components, are qualified per the AISC 7th Edition (Reference

[91). AWS D1.6 (Reference

[25]) was reviewed to ensure that any special qualification requirements associated with stainless steel welding were considered.

Since the weld allowables provided in AWS D1.6 are essentially the same as allowed for carbon steel welds under AWS D1.1 (Reference

[24]), no special adjustments are required to account for stainless steel.Rivets There are three areas in the strainer module where rivets are used as fasteners.

The disk faces are riveted to the perforated edge channels, the gap disk is fashioned into a ring using two rivets, and the end cover perforated plate is riveted to the end cover stiffener.

The rivets' capacities are based on testing. From Reference

[18], the capacities of the rivets are taken as the average value from six tests (six tests for shear and six tests for tension).

A factor of safety is then calculated according to the ASCE Standard (Reference

[22]) as supplemented by the AISI Code (Reference

[5]) accounting for the capacities being found experimentally via a small sample group (n = 6). The factor of safety used accounts for the load capacity variation in the test sample. This factor of safety will be used on these ultimate capacities for OBE. An increase of (1 + CT) is allowed for SSE, resulting in a FS / (1 + CT) for SSE.

U l Automated Engineering CALCULATION SHEET Page: 13 of 107 S c orp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 4.0 ASSUMPTIONS None 5.0 DEFINITIONS AND DESIGN INPUT 3 Define, ksi =-10 .psi kips = 10 .lbf kPa := 1000.Pa ORIGIN -I 5.1 Material Properties Material Types per Reference

[6g]: Perforated Plate: Core Tube: Radial Stiffeners:

Wire Stiffeners:

Rivets: Tension Rods: Bolts: Nuts: Washers: Spacer Sleeves: Cable Bracing: Filler Metal: Stainless Steel ASTM A-240, Type 304 Stainless Steel ASTM A-240, Type 304 Stainless Steel ASTM A-240, Type 304 Stainless Steel ASTM A-493, Type 302 (Drafted to a higher tensile strength)Stainless Steel ASTM A-240, Type 304 Stainless Steel ASTM A-276, Type 304, Condition B Stainless Steel ASTM 193 Grade B8, Class 2 Stainless Steel ASTM A-194, Grade 8 Stainless Steel ASTM A-240 or A-666 Type 304 Stainless Steel ASTM A-312, Type 304 Stainless Steel Type 304 Stainless Steel Electrodes ER308 or ER308L Design Temperature (Reference

[30])Max Operating Temperature (Reference

[30])TAL:= 190.F TOL:= 140.F Since AISC (Reference

[9]) does not provide material properties at elevated temperatures, the ASME Code (Reference

[3]) is used to determine material properties at elevated temperatures.

Properties are defined for three temperatures as shown below.All Type 302/304 Steels Modulus of Elasticity (Table 1-6.0, Ref. [3]), Yield strength (Table 1-2.2, Ref. [3])Ultimate Strength (Table 1-3.2, Ref. [3])ASME Allowable Stress (Table 1-7.2, Ref. [3])100 de-grees F Esc := 28300.ksi Syc:= 30.00.ksi Suc:= 75.0.ksi 140 degrees F Eso := 27925 ksi Syo:= 28.00 .ksi Suo := 73.4.ksi 190 degrees F Esa := 27650.ksi Sya:= 25.50-ksi Sua:= 71.4-ksi S := 17.9.ksi Note these properties are conservative for the Type 302 wire stiffeners which are drafted to a higher tensile strength than standard Type 302 stainless steels. Per Reference

[33], A-240 Type 302 steel has the same properties as A-240 Type 304, therefore use the properties for Type 304 from Reference

[3]. ,

Automated Engineering CALCULATION SHEET Page: 14 of 107 Services Corp Calc. No.: PCI-5464-S01 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No 0 Date: 08/25/06 ASTM A-276. Tvne 304. Condition B (Tension Rods)Sytr -Yield strength (Ref. [31 ]), Sytr:= 100.ksi Sut -Ultimate Strength (Ref. [31]) Sutr:= 125 .ksi Adjusting these values for temperature, using the same reductions as applied for the Condition A material.,Syo Sytr:= 'ytrSy-- Sytr = 93.3 ksi Suo Sutr:= SutrS Sutr = 122.3 ksi Suc ASTM ASTM 193 Grade B8, Class 2 (Bolting)Syb -Yield strength (Ref. [34]), Syb:= 100.ksi Sub -Ultimate Strength (Ref. [34]) Sub:= 125.ksi Allowable stresses for bolting materials are taken from Reference

[22] and are similarly scaled down for elevated temperature effects in Section 6.13.Other Miscellaneous Properties Ec -Modulus of Elasticity of Cable (Reference

[27])Density of stainless steel from Reference

[20], Poisson's Ratio of stainless steel from Reference

[20], Esa Shear Modulus of stainless steel at 190 OF Gs -.- v 2-(] + v)Density of water at temperature of 20 0 C (Ref. [12]), Coefficient of Thermal Expansion (CTE) of stainless steel, (going from 70OF to 190OF (Ref. [3], Table 1-5.0)Ec:= 12180.ksi lbf Psteel := 501--ft 3 v := 0.305 Gs = 10594 ksi lbf YH20:= 62.4.--ft 3 CTE := 8.77.106 Automated Engineering CALCULATION SHEET Page: 15 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 5.2 Strainer Geometry and Dimensions All data are per Ref. [6] unless otherwise noted.Perforated Plate Dimensions Mean thickness of 16 gage perforated plate as per Reference

[28]Hole diameter of perforated disk plate, Pitch distance between holes in disk plate (Center-to-center distance)tperf := 0.0595-in Ddisk.holes:=

0.085 -in Pdisk.holes:=

0.1406-in Disk Dimensions (Ref. M6al & [6b1)Strainer disk size Lldisk := 28.0.in L 2 disk:= 28.0.in Number of disks per strainer module Ndisk:= (6) (Ref. [6d])Strainer disk edge channel dimensions dchan =0.5in (Ref. [6h])bchan =0.5in LI Width of each middle disk assembly (Ref. [6h]) \,/ ýV'hex Wdisk: dchan + 2-tperf Wdsk = 0.619 in Figure 5.2-1 -Top view of Strainer Module Width of gap spacing between consecutive disks (Ref. [6h])Wgap:= l.0.in U Automated Engineering CALCULATION SHEET Page: 16 of 107 Services Corp Calc. No.: PCI-5464-S01 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 Welded Radial Stiffener Dimensions (All data per Ref. [6a & 6b] unless otherwise noted)The disks are supported by radial stiffeners which are welded to the core tube.Thickness of welded radial stiffeners Width of welded radial stiffeners Width of radial stiffener collar Width of top stiffener (bent-up) channel web Width of bottom stiffener (bent-down) channel web Width of top and bottom stiffener (bent) channel flanges Length of the channel portion of the radial stiffener tstfnr:= 0.25 -in wstfnr:= 2.25.in wcollar := 0.96875 -in WT.web:= 3.25.in WB.web:= 3.75. in wbent:= 1.75.in Lbent:= 2.875 -in Wbeflt]tstfri F'1 1_ I I' IJ(__________________________________________________________

I i II N, 1/ 11-t Wdisk IK !, 4-, dcablcv I Wgap OD Fý A'I NýF-'Po N.4 I I Fiur 522 Sd vewo SranrNodl Figure 5.2-2 -Side view of Strainer Module

_ Automated Engineering CALCULATION SHEET Page: 17 of 107 Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 Tension Rod Dimensions (All data per Ref. [6a & 6b] unless otherwise noted)Number of tension rods Tension rod diameter 0.9743 .in Tension rod tensile diameter ODtens:= ODrod -13 13 Outside diameter of pipe spacers (1/2" dia pipe, sch. 80)Thickness of pipe spacers Eccentricity between edge of disk and outer tension rod Nominal tension rod tightening torque Nrod:= 8 ODrod:= 0.5.in ODtens = 0.425 in (Ref. [9])ODspacer := 0.84.in tspacer := 0.147. in erod:= 0.9375.in Trod := 35-ft-lbf Core Tube Dimensions (All data per Ref. [6a & 6b] unless otherwise noted)Outer d ia meter of core tube Corrosion Allowance

/ Fabrication Tolerance Core tube wall thickness (16 ga.)Core tube wall thickness after allowance ttube := tl6ga -2 tca Outer diameter of disk gap Number of rows of core tube holes Number of core tube holes per row Radial stiffener to core tube weld thickness Radial stiffener to core tube weld length (per individual weld)Outer diameter of the debris stop Inside diameter of core tube sleeve (at base)Width of Core Tube Sleeve Core tube sleeve wall thickness (16 ga.)ODtube:= 13.25 -in tca := 0.0-in tl6ga := 0.0598.in ttube = 0.0598 in ODgap:= 15.75 -in Nhiole:7 Nhole.circ:=

4 tw.ct:= 0.0625 in ww.ct:= 1.5.in ODdebris:=

15.25 -in Dsleeve := 13.375 in Wsleeve:=

2.5-in tsleeve := 0.0598-in (Ref. [9])(Ref. [9])(Ref. [6h])(Ref. [6j])(Ref. [6j])(Ref. [6i])(Ref. [6i])(Ref. [6i])The orientation of the hole along the circumference 0 90 180 deg 180, ,270)

Automated Engineering CALCULATION SHEET Page: 18 of 107 Services Corp Calc. No.: PCI-5464-So1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sumin Strainers Reviewed By: Kishore D. Patel Safety Related Yes E- No D Date: 08/25/06 Rivet Dimensions (All data Der Ref. [6h1 unless otherwise noted)Number of edge channel rivets per disk side Rivet head radius Number of intermediate disk face rivets Number of inner gap rivets holding the hoop together Number of end cover rivets Eccentricity between the edge channel rivets and the adjacent edge of disk Approximate offset from line from center of core tube and center of outer rod N1 rivet := 8 N 2 rivet:=Crivet := .1875in (Ref. [6g])Nrivet.face

= 0 Nrivet.hoop:=

2 Nrivet.end

= 16 (Ref. [6i])erivet := 0.3125.in eoff:= 1.75.in (not show 8 n on dwg.)Internal Wire Stiffener Dimensions (All data per Ref. [6h] unless otherwise noted)Number of intermediate circumferential stiffeners Diameter of radial wire stiffeners (7 ga)Maximum diameter of circumferential wire spacers (8 ga)Inner circumferential stiffener width Lcirc.in:=

ODtube + 1.5.in Outer circumferential stiffener width (Side 1) LI circ.out := L1 disk -1.875 .in Outer circumferential stiffener width (Side 2) L 2 circ.out:=

L 2 disk -1.875.in Corner distance for outer circumferential Ncirc:= I dwire.rad:=

0.177.in (Ref. [6a/b])dwire.circ:=

0.162.in (Ref. [6a/b])Lcirc.in = 14.75 in Li circ.out = 26.125 in L 2 circ.out = 26.125 in Lcirc.cor

= 1.5.in Other Miscellaneous Dimensions (All data per Ref. [6a & 6b] unless otherwise noted)Length of hex coupling Lhex:= 2.5.in Outer dimensions of 1 1/6" Hex Coupling (C is point-to-point, F is flat-to-flat)

Chex:= 1.25.in Fhex := 1.0625.in Effective outside diameter of hex couple ODhex:= 0.5.(Chex

+ Fhex) ODhex = 1. 15625 in Inside diameter of hex coupling lDhex:= 0.50.in* 1 1/6" hex bar is 1 1/6" flat-to-flat.

Per AISC (Ref. [9]), this is equivalent to a 5/8" heavy hex nut which has a 1.25" C dimension (corner-to-corner)

Automated Engineering CALCULATION SHEET Page: 19 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes WE No D Date: 08/25/06 Eccentricity between outer tie rod and hex coupling Nominal diameter of connecting bolts Cross Section Metal Area of Bracing Cable Effective Diameter of cross bracing cables dcable -Acable End Cover Stiffener Dimensions (All data per Ref. [6i1 unless otherwise noted)Number of radial spokes Number of circumferential rings Thickness of spokes and rings Width of radial spokes Width of circumferential rings ehex:= 1.875 -in ODbolt:= 0.5.in Acable 0.029 in2 (Ref. [27])dcable = 0.192 in Radius of circumferential rings Mean thickness of end cover mounting tabs (11 ga.)Width of end cover mounting tabs End cover tab-all around weld thickness Cap plate width Mean cap plate thickness (11 ga.)Cap plate diameter Leg size for end cover stiffener weld Nspoke:= 8 Ncirc.end

= I tend := 0.375 in Wspoke:= 0.25-in wcirc:= 0.25.in/0.5 Rcirc.end

= .125 in tl1ga := 0.1196.in (F wend.tab:=

1.25.in tw.tab:= 0.125-in wcap:= 2.1875.in

-0.12 tcap:= 0.1196.in (F Dcap:= 13.5.in tw.spdr:=

0.125 -in[9])5.in[9])

U Automated Engineering CALCULATION SHEET Page: 20 of 107 SServices Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes W No D Date: 08/25/06 Core Tube Hole Pattern (All data Der Ref. [6i1 unless otherwise noted)The hole/slot distributions along the length the core tube are given in terms of dimensions H ( the width of the slot (W on the PCI drawing))

and L2, the length of the slot (H on the PCI drawing).

The length of the slot (L2)is orientated along the axis of the core tube. There are four holes around the circumference of each row.There are Nhole, number of rows. H is provided in array format, where the rows are the hole locations, the first row being the lowest hole, and the last being the highest hole. The first column represents the holes associated with the 0 and 180 degree locations of a module, and the second column represents the holes associated with the 90 and 270 degree locations of a module. The hole size are based on an average 6 disk strainer module. Use the middle 6 disk module of the 4 module stack.k:= I..Nhole, j:= 1..2 90 deg 0 1 90 180 1 270 H :='2.70 2.89 3.09 3.33 3.61 3.98 2.70 2.89 3.09 3.33 3.61 3.98)-in Lug hig fL~ =jrL2 HI EID 4I I V L2 :=0.958 -in Luig: 0.5-in rhole =min (2 ,0.25 -in)Figure 5.2-3 -Partial View of Core Tube Layout (Figure is a partial view of complete layout, see Ref. [6j])Note the holes at 0 degrees and 180 degrees are the same size, and the holes at 90 degrees and 270 degrees are also the same size. The maximum hole sizes for any module are given below.0 90deg Hmax:= (8.88 8.88 ).in L 2 max:= 0.958.in Automated Engineering CALCULATION SHEET Page: 21 of 107 S Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No DI Date: 08/25/06 6.0 6.1 CALCULATIONS Weight Calculations The weights of the strainer components are calculated piece by piece Core Tube Length of core suction tube (stacked-disk length only), Lstrnr:= Ndisk.(Wdisk)

+ (Ndisk -i) Wgap Length of core tube extension (beyond active strainer length, including gap)Lstub := 1.(Lhex + 2"tstfnr)Overall effective length of core tube (includes gap between core tube)Ltube : Lstrnr + 2 .Lstub Inner diameter of perforated core tube, lDtube:= ODtube -2.ttube Weight of the core tube not considering the holes (not including stub pieces)Lstrnr= (8.1. in K10.33)Lstub = 1.50 in (11.71)Ltube = I .1 in (13.33)IDtube 13.1 in Wttube 6.3 lbf"2.53 2.53 2.71 2.71 2.91 2.91 Ahole 3.14 3.14 3.4 3.4.3.76 3.76 Wttube := Psteel*.4-(ODtube2

-Dtube2) Lstrnr Surface Area of the holes Ahole := (H.L2) -(4.rhole -7u~rhole.2 In The total volume of holes per module (averaged between the upper and lower modules), is Nhole.circ~ttube 2 NholeI VOlholes:=

2 Z Aholei,j j~l i=1 VOlholes = 4.41 in3 U1M Automated Engineering CALCULATION SHEET Page: 22 of 107>Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 VOlholes Wtperf.tube:=

Wttube -0.5PVOlholes

'Psteel Wtperf tube = 5.0) lbf Core Tube Sleeve Number of sleeve Nsleeve := 4 Wtsleeve::

Nsleeve " .[(Dsleeve

+ 2.tsleeve) 2-Dsleeve2]

Wsleeve P steel Wtsleeve = 7.3 Ibf Perforated Plate The disks, outer rims, and inner gaps are made from perforated plate. Calculate the percentage of open area for the perforate plate (perf plate).Perforation ratio (open area) of perforated disk plates, Disk plate area Open area 2 Pdisk.holes .sin (60.deg)Adp 2-2 7u-Ddisk.holes 3 Aop:=4 6 Adp = 0.0086 in 2 Aop = 0.0028 in 2 PRdisk = 33.1 %Perforation ratio PRdisk := A-p Adp The perforated plate stresses are calculated based on an equivalent solid plate. Equivalent solid plate stresses are multiplied by the ratio of the hole spacing (pitch) divided by the ligament width (see Reference

[4]).Therefore, the perforated plate stress multiplier is: Ligament width between holes in perf plate, hdisk.holes:=

Pdisk.holes

-Ddisk.holes The stress increase ratio for perf plate is therefore Pdisk.holes Kpp.- hdisk.holes hdisk.holes

= 0.0556 in Kpp = 2.53 I Page: 23 of 107 Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes W No D Date: 08/25/06 The weights of the perf plate are broken down into three parts. The disk face plates, the disk outer channels, and the disk inner gaps.Wtface:= LldiskL 2 disk- -.ODgap .2.tperf.(Ndisk).(l

-PRdisk).Osteel Wtface 895) Ibf Wtedge:= (dchan + 2.bchan).tperf.2.(Lldisk

+ L 2 disk -2.bchan).Ndisk.(1

-PRdisk)-Psteel Wtedge C 1 3.Jlbf:ý .ODgap~tper.(l

-PRdisk)'Psteel.(Ndisk-

).(Wgap) Wtgap C 2.9) lbf Welded Radial Stiffeners The weight of the corner welded radials is calculated below The length of the stiffener from the outside of the collar to the outertie rod (beginning of bent up channel) is/LI circout 2 (L2circ.out 2 _ (ODtube 1 Lsfnr: + + Wcollar ( n16 Therefore, the weight of the radial stiffeners (including collars and bent up channels) is Lstfnr = 10.82 in Wtstfnr [4 [4.(4.wbent

+ WT.web + WB.web -4.tsffnr).Lbent

+ 2 Wsffnr Lstfnr] -tstfnr Psteel] ...1+2't 'ODtube + --in + wcolla$ 'wcollar'tstfnr'Psteej Wtstfnr = 31.28 lbf (Note the steel removed for holes is not subtracted, rather it takes the place of the weight of the nuts)

Automated Engineering CALCULATION SHEET Page: 24 of 107 Z7 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes No D Date: 08/25/06 Intermediate Wire Stiffeners The intermediate wire stiffeners are made up of two layers of radially orientated stiffener wires supporting the perforated plate, separated by a single layer of stiffener wire orientated in the circumferential direction.

The radially orientated stiffeners are arranged in a zig-zag pattern. Additionally, there are corner radial stiffeners that are curved around the tension rods which hold the stiffener wires in place. The radial wires support the perforated plate for suction pressure.

They are not physically attached to the perforated plate; they only support the plate through bearing. The circumferentially orientated stiffeners are there to support the radial stiffeners.

Welds connect the radial wires to the circumferential wires, but these welds are considered non-structural as the load is transferred in bearing. The circumferential stiffeners are simply in compression through their thickness and serve to maintain the spacing between the radial wires for the suction pressure load case.The wire pattern is designed such that the outer bends are aligned with the edge rivets. The rivets are spaced equally along each edge, with the first and last rivets offset from the edge a certain distance.

Therefore, in order to determine the spacing of the wire stiffeners, this offset must first be calculated.

The distance from the edge of the disk to the first edge channel rivet is found by drawing a line from the center of the core tube to the center of the outside rod. Offsetting that line by 1.25" in both directions and finding the points where these lines intersect with lines drawn parallel with the disk edges that are offset 0.25" inward, thelocations of the first edge channel rivets for side 1 and side 2 are found.(L2disk- 2.erod" C~disk.1 :=atan .~isk--dk y Ll disk erod)(Ll disk- 2.erod" tdisk.2 := n 1L 2 disk- 2"erod)adisk.1 = 45.00 deg Otdisk.2 = 45.00 deg drivet.edge.1

= eoff-sin((adisk.1)

...+ erod -'erod -eoff'cos(c-disk'l)

-erivett tan(atdiskl1) drivet.edge.2 eoff.sin(axdisk.2)

...+ erod -'erod -eoff'cOs(adisk'2)

-erivett d+ erod -tan(acdisk.2)9 drivet.edge.1

= 2.787 in drivet.edge.2

= 2.787 in

_ Automated Engineering CALCULATION SHEET Page: 25 of 107 Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No El Date: 08/25/06 Corner Radial Circumferential Stiffener Stiffener Stiffener eoff Intermediate

--------------

CircumferentialStiffener V2 S1 d.rivet.edge.1I I--\ S 2 rad d.rivet.edge.2 Figure 6.1-1 Internal Wire Stiffeners (actual configuration may differ)

_ Automated Engineering CALCULATION SHEET Page: 26 of 107>7 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 Therefore, the spacing of the wire stiffeners is Li disk -2.drivet.edge.1 N 1 rivet -I L 2 disk -2"drivet.edge.2 aN 2 rivet -I S1 rad = 3.20 in S 2 rad = 3.20 in The length of each radial wire (not including corners) is calculated below, i we rad 2 L1 circ.out -Lcirc.in 1 2 L1lwire :- +Li wire = 5.91 in ir 1S2rad L2circ.out

-Lcirc.in 2 L2wire := 1( 2 ) + ( 2 2 L 2 wire = 5.91 in The total length of the zig-zag radial wires is calculated below. 3/4" is added to each spoke to account for the extra material overhanging the circumferential support wires. A 1/2 length segment is considered on each end.Lradial:= (Li wire + 0.75 .in).(Nlrivet

+ 4) + (L2wire + 0.75.in).(N2rivet

+ 4)Lradial = 159.81 in The corner radials wrap around the corner tension rod spacers to hold them in place, therefore their length is calculated as follows Lcorner:=

2. _[ E :L1c u.iout L2circ.out.

ODgap 3ODspacer+

3.t.2+. 2 + (2 .(2 ODsac dwirerad -+ " Wtradial:=

2-Ndisk. -dwire.rad (4.Lcorner

+ 2.Lradial).Psteel Lcorner = 30.24 in b37.7)Wtradial = 44.0)The circumferential stiffener wires consist of a square shaped inner wire, and rectangular shaped outer wire offset slightly in from the edge of the edge channel with the corners trimmed to clear the outer tension rods.Additional circumferential wires (if used) are approximately equally spaced and their length is considered equal to the average length between the inner and outer wires.Linner := 4.Lcirc.in Louter:= 2-(Licirc.out)

+ 2.(L2circ.out)

-4.(2 -VY).Lcirc.cor Linner = 59.00 in Louter = 100.99 in Automated Engineering CALCULATION SHEET Page: 27 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 2 Linner ++/-Louter]Wtcirc:= Ndisk-* dwire.circ

.Linner + Louter + Ncirc- 2 steel Tension Rods Lrod := Lstrnr + 2.in The total weight of the tension rods is Wtrod:= 8"Lrod' (ODrod ')Psteel Cross Bracing Cables Lcable := 4.(F Lldisk 2 + Lstrnr 2 + FL2disk 2 + Lstrnr2)it 2 Wtcable :=- .dcable .Lcable'Psteel 4 C8.6 /Wtcirc = 10.0) bf C 10.71 ) in Lrod =(12.33 )Wtrod = I4 lbf ( 5.6)Lcable \238.77) in Wtcable = 2.0 Ibf C(8.00 Lspacer =9.50) in lDspacer 0.55 in Wtspacer = 5.9 lbf Spacers Lspacer:=

Ndisk'dchan

+ (Ndisk -1).Wgap IDspacer:=

ODspacer-2.tspacer Wtspacer:=

8 (ODspacer2-

_Dspacer 2).LspacerPsteel Module-to-module connectivity Wthex:= 2.4.E-.(ODhex2).Lhex.Psteel Wthex = 6.11bf (Use outside diameter to account for both hex nuts and connecting bolts. Multiply by two to account for bolt heads and cross bracing cable connection hardware)End Cover-PRdisk) + 7iDcap'wcap'tcap

... "Psteel Ncirc.end+

I tDcap + Ie (2.Rcirc'endn) t(tend'wspoke) n=l Wtec = 8.1 lbf U11M Automated 1 Engineering CALCULATION SHEET Page: 28 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Sirainers Reviewed By: Kishore D. Patel Safety Related Yes NI No ElI Date: 08/25/06 Total Weiaht and CG of Strainer Component Core Tube Disk Faces Disk Edge Channels Disk Inner Gaps Welded Radial Stiffeners Radial Wire Stiffeners Circumferential Wire Stiffeners Tension Rods Rod Spacers Cross Bracing Cables Hex Couplings End Cover Sleeve Total weight of one strainer module Weight Wtperf.tube

6.8) lbf Wtface 1.1 I lbf (95.1)Wtedge , ,,Ibf= 2.9) lbf Wtgap 3.4 Wtsffnr = 31.3 lbf Wtradial = C7.0 lbf C8.6 Wtcirc = 10.0) bf Wtrod = 4.9 lbf Wtspacer = 5.1 lbf Wtcable = 2.0 lbf Wthex = 6.1 lbf Wtec = 8.1 lbf Wtsleeve = 7.3 lbf (6 disk module)(7 disk module)(197/Wtstrnr = 197) lbf (225)(not including end cover or sleeve)Wtstrnr:

Wtperf.tube

+ Wtface + Wtedge + Wtgap + Wtstfnr ...+ Wtradial + Wtcirc + Wtrod + Wtspacer + Wtcable + Wthex (Note that the weight of the sleeves that connect module to module were not included in the GTSTRUDL model. This weight is small and can be neglected)

I

_/ Automated Engineering CALCULATION SHEET Page: 29 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sumin Strainers Reviewed By: Kishore D. Patel Safety Related Yes N No Fi Date: 08/25/06 6.2 Strainer Loads The loads on the strainer are comprised of weight, pressure, and dynamic loads. The applicable loads and load combinations are described in Section 3.0.6.2.1 Pressure, Weiaht. and Thermal Loads Two weight loads are applicable.

This includes the weight of the strainer components themselves (WT), and the weight of the debris which accumulates on the strainer (WD). The weight of the strainer modules is calculated in Section 6.1 and is summarized below.WT : Wtstrnr WT = (125 lbf (6 disk module)(7 disk module)(not including end cover)The weight of the debris per strainer module used in the analysis is shown below. These values are slightly higher than the actual debris weights calculated in Reference

[23]. This weight is included in the GTSTRUDL model and is spread out over the surface area of the perforated plate. These values far exceed the 25 pounds per square foot minimum weight specified in Reference

[30].WD := 259 I'lbf (.303)(6 disk module)(7 disk module)(Reference

[23])(actual values from Reference

[23] are 239 lbf for the 6-disk module, and 280 lbf for the 7-disk module. Use of these higher weights is conservative)

Thermal expansion loads are zero because the strainers are essentially free standing structures and for the most part free to expand without restraint.

In the lateral direction, both the strainers and the top of the plenum expand about equally since both are made from stainless steel. Therefore thermal loads are considered negligible and are taken equal to zero.The differential pressure load (DP), is pressure load across the perforated plate during accident conditions when the strainers are covered with debris. This is conservatively based on the maximum allowable hydrostatic pressure drop across the debris covered strainers provided in Reference

[1] and [29].DP := 3.5.ft.YH20 (Reference

[1] and [29])DP = 1.52 psi Pressure is for the most part equalized on all strainer surfaces, except that the pressure force on the strainer end cap of the top strainer modules is not balanced.

This is applied in GTSTRUDL as a pressure force to the four joints at the intersection of the core tube and the top radial stiffener of the top module (Joints 4161 to 4164). The magnitude of the pressure force per joint is: 1 71 2 Pec:= DP'-'Dsleeve 4 4 Pec = 53.3 lbf U Automated Engineering CALCULATION SHEET Page: 30 of 107 Services Corp Caic. No.: PCI-5464-SOI Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes W No D Date: 08/25/06 6.2.2 Seismic Inertia Loads A response spectra analysis is performed to analyze the seismic inertia loads. The seismic analysis methodology is detailed in Section 2.0. The response spectra are taken from Reference

[2]. The 2%damping spectra at Elevation 703' is used for the OBE load case, and the 3% damping spectra is used for the SSE case. The response spectra in the horizontal direction are enveloped at each frequency for the E/W and N/S directions.

These enveloped spectra are shown in the figures below: OBE Horizontal Response Spectra (2% Damping)Elevation 703 (Broadened) 0*1-'(U (.)C., 0.6 0.5 0.4 0.3 0.2 0.1 OBE 2%....... OBE 2%-OBE 2%E/WL-N/SC 7 -----0 0 5 10 15 20 25 30 35 40 Frequency (Hz)Figure 6.2-1 OBE Horizontal Response Spectra U l Automated M Engineering CALCULATION SHEET Page: 31 of 107 Services Corp Caic. No.: PCI-5464-S01 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D1 Date: 08/25/06 SSE Horizontal Response Spectra (3% Damping)Elevation 703 (Broadened)

C 0 0 0 U C.)1 0.8 0.6 0.4 0.2--- -SSE 3% E/W\/....... SSE 3% N/S SSE 3% Envl 0 0 5 10 15 20 25 30 35 Frequency (Hz)40 Figure 6.2-1 SSE Horizontal Response Spectra The actual digitized data points can be seen in the GTSTRUDL input file included as Attachment A. The peak of the response spectra are shown below: h := I .. 2 (h = 1 corresponds to OBE, and h = 2 corresponds to SSE)=0.541 OBE ah 0.864 SSE 0:= .0335 ) OBE (0.562 SSE U lAutomated Engineering CALCULATION SHEET Page: 32 of 107>Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes [E No D Date: 08/25/06 6.3 Calculation of Strainer Surface Area The enclosed volume of one strainer module (including 1/2 the core tube volume between Ldisk:= Wdisk.Ndisk Lgap:= Wgap.(Ndisk (total length of all disks)modules) is, Ldisk (3.71 ) in.(5.00~Lgap K6.00) in I) (total length of all gaps)The projected area of the strainer modules in each of the three directions Aproj.x:=

Ldisk-L 2 disk + Lgap.ODgap

+ Lstub.ODtube Aproj.y:=

Lldisk-L 2 disk Aproj.x -1.64 Aproj.y = 5.44 ft 2 Aproj.z = 1.4 ft2 Aproj.z:=

Ldisk.Ll disk + Lgap'ODgap

+ Lstub'ODtube The approximate strainer surface area is calculated below (note this is for structural purposes only, this value may somewhat differ from that used in the head loss calculations which is calculated more accurately)

As.gap:= lT.ODgap.Wgap.(Ndisk

-1)As.edge := 2-(Lldisk

+ L2disk).Wdcisk.Ndisk As.end:= (Ll disk.L 2 disk ODtube2)

As mid =LI disk. L 2 isk 400gap As.gap = .2. ft (2.89 2 As'edge = 23.37) ft As.end = 4.49 ft2 As.mid = 4.09 ft 2 As = 54.50 ) 2 (~63.50)As:= As.gap + As.edge + As.end.2+ As.mid.(2.Ndisk

-2)

U Automated Engineering CALCULATION SHEET Page: 33 of 107 Services Corp Calc. No.: PCI-5464-So1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 6.4 GTSTRUDL Model 6.4.1 General Description The analysis of the strainer modules is performed using GTSTRUDL.

Due to the similarity between modules, only one stack of strainer modules is analyzed.

The modules are essentially identical with the only difference being the hole sizes in the core tube. The critical stack is the taller one, composed of one 7 disk module, and three 6 disk modules stacked on top of each other. The modules are connected with hex couplings at the four comers and the core tubes are connected with sheet metal sleeves. These sleeves can take shear loads and axial compression loads (through bearing) but not tension. The sleeves are considered as axial supports for the downward vertical loads (Pressure, Dead Weight, and Debris) but are released for seismic load combinations (since they do not resist tension).

Conservatively, the sleeves are also released for shear therefore all shear loads are transferred through the hex couples. Note, the bands have a fairly large capacity in shear so there is not a concern that the bands will fail in shear due to relative lateral motion between the core tubes. The GTSTRUDL model contains the main structural elements of the module. The_perforated plate and internal wire stiffeners are not included in the model (except for their mass). The following member types are included in the model: Member Type Member Numbers Welded Radial Stiffener Arms 'RADS1'to'RADS64' Collar (Debris Stop)Bent Up Portions of Stiffeners Hex Couplings Outer Tension Rods Outer Rod Spacers Inner Tension Rods Inner Rod Spacers Core Tube'COL1 to 'COL64BENT1' to 'BENT32' and 'PAl to 'PA32' 'PC9' to 'PC40' 'PAB1 to 'PAB32' and'PBC9' to 'PBC40HEX1 to 'HEX32OROD501' to 'OROD529' (increment range by 100 for each additional strainer)'SPCR501' to 'SPCR529' (increment range by 100 for each additional strainer)'IROD10l' to 'IROD129' (increment range by 100 for each additional strainer)'SPCR10 1'to 'SPCR129' (increment range by 100 for each additional strainer)'CT1' to 'CT29'Core Tube to Core Tube Sleeve 'CTS1' to 'CTS3'Edge Channels Cross Bracing Cables Core Tube Rigid Links Links Between Modules'EC100l' to 'EC1 112' 'EC2001' TO 'EC2096' 'EC3001 TO 'EC3096EC4001' TO 'EC4096CABLE1' to 'CABLE32' and 'PBI' to 'PB16RIGID1' to'RIGID32'

'ELMNTI' TO 'ELMNT16' and 'ELMNT17' to 'ELMNT20' I Page: 34 of 107 Caic. No.: PCI-5464-SO1

('lont T) F- Pnfnr Cn rnnror' I-,'Rouicidnn I t*n nh. I '..i I.I IILV, -tA 6 Ii, /.Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No [D Date: 08/25/06 A solid plot of the GTSTRUDL model is provided below. Additional single line plots are included in Attachment C which show the specific member numbers. The model is displayed group by group in these plots such that the numbers are readable without overlapping one another.Y x .z Figure 6.4-1 GTSTRUDL Model (Solid Model)

Client: Performance Contracting Inc.Station: Watts Bar Unit 1 Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Safety Related Yes E No El Page: 35 of 107 Calc. No.: PCI-5464-SO1 Revision:

2 Prepared By: Curtis J. Warchol Reviewed By: Kishore D. Patel Date: 08/25/06 A couple stick model representations are shown belowwith the overall dimensions given y z Ix Figure 6.4-2 GTSTRUDL Model (Stick Model Side View)

U Automated Engineering CALCULATION SHEET Page: 36 of 107 Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 IN YF x z Figure 6.4-3 GTSTRUDL Model (Stick Model Plan View)

Page: 37 of 107 Calc. No.: PCI-5464-SO1 Revision:

2 Client: Performance Contracting Inc.Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No 0 Date: 08/25/06 Tension Rod / Spacer Modeling The tension rods and spacers are modeled on top of one another using a second set of nodes with identical coordinates.

The rods are not connected to the spacers, rather the JOINT TIES and SLAVE RELEASES commands in GTSTRUDL are used to constrain the relative motion between these coincident nodes. The nodes are allowed to move relative to one another along the axis of the rods, but are constrained to move together in the lateral directions.

The spacers have the capacity to carry a certain amount of lateral loads because they are pre-compressed.

As long as the bending moments in the spacers do not result in a tension stress in excess of the preload, these spacers can carry lateral loads. Once the bending moment reaches this point (a net tension in the extreme fiber of the spacer), the spacers can take no additional lateral loads and any further lateral loads are carried solely by the tension rods. This is discussed in more detail in Section 6.5.Radial Stiffeners The external radial stiffeners are cut from one plate in a "cross and collar" pattern, where all four stiffener legs are continuous with a collar that goes around the core tube. This collar is then welded to the core tube and provides the structural backbone and the primary torsional resistance capacity for the modules. The radial arms are connected to the collar which is modeled as an octagon to represent the curved shape. A 4 1/2" wide section is modeled from the collar/arm intersection to the outside of the core tube. This piece represents the portion of.the collar that is welded to the core tube by two 1 1/2" long welds with a 1 1/2" gap between welds (4 1/2" wide total)for each radial rib.Rigid Link Modeling In GTSTRUDL, the core tube is supported at its ends by rigid links (Group "RIGID") that extend from the centroidal axis of the core tube to the external radial stiffeners (essentially between the weld pairs of the debris stop to the core tube). The properties of these rigid links are inputted manually such that they absorb no axial load or torsional moment but do transfer shear loads. The reasoning is that the debris stop creates the load path from one side of the strainer module to the other as it is much stiffer than the flexible 16 gauge thick core tube. Bending in the axial direction of the core tube is released for the rigid links at the external radial stiffener connection as this bending will be resisted by the debris stop, and the inner tie rods and spacers.Additional flexible links connect the four hex couplings at the module intersections.

These links are used to easily find the displacements and rotations at the intersection between each module. This data is used in a separate calculation for the plenum such that the strainer modules can be represented by simple stiffness matrices.

The links are modeled with very small properties so they do not effect the response of the model.They are also pinned at the connection to the modules. This ensures these members do not pick up any load, yet remain straight such that a single node at the center of these links can be used to determine the rotations at the ends of the modules. The links at the very bottom connect the four elastic support points and are used to represent the mass and stiffness of the plenum. They are modeled as 16" wide 1/2" plates to represent the top cover plate of the plenum, and are given mass to represent the mass of the plenum acting on the elastic supports (see Section 6.4.6 for additional information).

_ Automated Engineering CALCULATION SHEET Page: 38 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E- No -Date: 08/25/06 Cross Bracing Cable Modeling The cross bracing cables are modeled as solid circular rods with a cross sectional area equal to the actual metal area of the cable. There are four cables per module that run from one upper corner, diagonally down to the adjacent corner at the bottom, and then back up to the opposite comer at the top. The cables are free to slide through tube guides at the bottom corners. This sliding action is allowed in the GTSTRUDL model. This is accomplished by the use of the JOINT TIES command.Each cable is composed of three sections, the two main diagonals, and a short section at the bottom corners. The cables have their own nodes at this lower corner-and there are releases at the ends of the short section allowing the cable to bend. The nodes at the ends are connected to different nodes that share the same coordinates that are attached to the radial stiffen ers. The JOINT TIES command forces these nodes to displace together except that, in the direction parallel to the short section, the cable can slide relative to the radial stiffener.

This represents the actual behavior of this cable connection.

The cables are only allowed to take tension sliderelative to loads. A static horizontal acceleration run is Nodes are joint tiedi used to determined which cables experience to the welded radial tension, and which cables experience but released parallel compression.

Any cables that experience to the short cable compression are removed from the model for the seismic runs using an INACTIVE command. Figure 6.4-4 Modeling of Cables For deadweight, and the vertical seismic case, conservatively, all cables are inactive.

For the horizontal seismic case, one half of the cables are removed (the ones showing compression in the static case). Figure 6.4-5 on the next page shows which cables are active for the horizontal seismic case. Note the eigenvalue analysis which determines the frequencies and mode shapes are run for the same cable configuration as is used in the analysis of that load combination (i.e. no cables for vertical seismic, and only the X-tension cables for lateral seismic.Note that the cables are not preloaded, however the cables are tightened to the point where all the slack is removed such that they will be active for the lateral seismic cases.

U Automated Engineering CALCULATION SHEET Page: 39 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Caic. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E- No 0 Date: 08/25/06 y z Figure 6.4-5 GTSTRUDL Model (Active Cables for Horizontal Seismic)

Page: 40 of 107 Calc. No.: PCI-5464-SOI Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes WE No El Date: 08/25/06 6.4.2 Member Properties Most of the member properties are defined using standard shapes available in GTSTRUDL.

However, for some of the members equivalent sections are defined to account for the holes in the members (i.e. core tube, and edge channels).

Welded Radial Stiffener Properties The welded radial stiffeners members are made up of two separate cross sections.

The first is a simple flat plate with a rectangular cross section, representing the portion between the collar and the bent-up channels.

The second is a channel cross section used to replicate the bent-up channels at the ends of the radial stiffeners.

The properties are input into GTSTRUDL usinga user defined table. Only the width and thickness are required for the rectangular cross section while the channel cross section requires the flange and web widths and thicknesses.

GTSTRUDL then internally calculates all of the cross sectional properties for that shape. Since this is a user defined table which is not included in the verification of GTSTRUDL, these properties are printed out in the output and manually verified to be correct for each size. The applicable sizes are: Welded radials Top bent-up channels Bottom bent-up channels 1/4" thick x 2 1/4" wide Flange: 1/4" thick x 1.75" wide Web: 1/4" thick x 3.25" wide Flange: 1/4" thick x 1.75" wide Web: 1/4" thick x 3.75" wide Tension Rods and Spacer Properties The tension rods are solid round bars with a circular cross section. The spacers, are hollow round bars with a pipe like cross section. The properties are input into GTSTRUDL using a user defined table. Only the outer diameter and thickness (for the spacers) of the members are required and then GTSTRUDL intemally calculates all of the cross sectional properties for that shape. Since this is a user defined table which is not included in the verification of GTSTRUDL, these properties are printed out in the output and manually verified to be correct for each size. The applicable sizes are: Outer Tension Rods Inner Tension Rods Outer Rod Spacers Inner Rod Spacers 1/2" diameter solid round bar (see note below)1/2" diameter solid round bar (see note below)0.84" outer diameter, with 0.147" thickness 0.84" outer diameter, with 0.147" thickness Note the tensile diameter of 0.425" (Reference

[9]) is used for the elements at the end of the rods to account for the threads in these locations.

U i Automated Engineering CALCULATION SHEET Page: 41 of 107 SServices Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes -No D Date: 08/25/06 Core Tube Properties This section calculates the core tube properties (i.e. effective cross-sectional properties) including the effect of holes. These properties are used as input in the GTSTRUDL model.Calculate the reduction in metal area of the cross section due to holes. The last rowof the array is used to calculate the effect of the largest holes in any module.Arearedk := 2"ttube-(Hk, I + Hk,2)ArearedNhole1+1

= 2"ttube'(Hmax i, + Hmax 1 , 2)Area red =0.65" 0.69 0.74 0.80 0.86 0.95.2 k2 := I .. Nhole1 + I The reduced area due to the holes is, Atube:= 4 .(ODtube2

-Dtube2)Atube = 2.48 in 2 1.83 1.79 1.74*.2 Ared 1.68 in 1.61 1.53 ,0.35 Ared:= Atube -Areared Moment of inertia of the core tube without holes, Itube:= .(ODtube4 -IDtube4)Mean Radius of Core Tube, ODtube + IDtube Rmean:=4 Itube = 53.89 in 4 Rmean = 6.60 in UAutomated Engineering CALCULATION SHEET Page: 42 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes El No D Date: 08/25/06 Moment arm of hole around x-axis (from Core Tube center to Core Tube slots), x: Rmean.sin

+ 4))y: Rmean-COS( 0+1 2 x2:= x 2 Moment of Inertia of Core Tube Holes (neglecting I about their own centroids), ihole.x .Areared ).x 2 T.Nhole.circ) 4 Iholes.xk 2 Y, Ihole.xk2,j j=I (Areared ) T yNhole.circ).Y (4.66 '4.66 x Iin-4.66 ,-4.66, 4.66 '-4.66 Y -4.66 in ,4.66 , 3.51 3.76 4.02'hole.x = 4.33 4.69 5.18 11.55 14.05 15.03 16.07 Iholes.x = 17.32 18.78 20.7 ,46.19 3.51 3.76 4.02 Ihole.y = 4.33 4.69 5.18 11.55'21.75 'x2 217 in2 21.75 21.752"21.75)y2 !1 75jin2 21.75, ,ý21.75, 3.51 3.76 4.02 4.33 4.69 5.18 11.55 3.51 3.76 4.02 4.33 4.69 5.18 11.55 3.51 3.76 4.02 4.33 4.69 5.18 11.55.4 in}.4 in J 3.51 3.76 4.02 4.33 4.69 5.18 11.55 3.51 3.76 4.02 4.33 4.69 5.18 11.55 3.51 3.76 4.02 4.33 4.69 5.18 11.55.4 in U Automated Engineering CALCULATION SHEET Page: 43 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit I Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No i Date: 08/25/06 4 lholes.'yk 2 I Ihole'Yk2,j j=i Reduced moment of inertia due to holes, I holes.14.05 15.03 16.07 y 17.32 18.78 20.7 ,,46.19,,"39.85 38.86 37.82.4 36.57 in 35.11 33.19 7.70.4 in Ired ': Itube- (.holes.x + Iholesy-2)Ired =An equivalent moment of inertia for the core tube is determined by averaging the moment of inertia of the various full and reduced sections over their length. Once the equivalent moment of inertia is determined, an equivalent thickness can be determined.

Nhole I Y (Iredi'L2)

+ Itube'(Lstrnr

-L2"Nhole)i =I lavg:=lavg = 42.68 in 4 Lstrnr EQID.I :-ODtube4

_ 64. lavg 4 ODtube -EQID.I teq 2 EQID.I = 13.16 in teq = 0.047 in vs. ttube = 0.060 in U Automated Engineering CALCULATION SHEET Page: 44 of 107 4 ' Services Corp Calc. No.: PCI-5464-S01 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes W- No D Date: 08/25/06 Therefore, this equivalent thickness is used in the GTSTRUDL model to account for the holes in the core tube.The area and section modulus of the equivalent core tube is calculated as follows, Aeq:= "-.[ODtube2

_ (ODtube -2 teq)2]S.[ODtube 4- (ODtube -2.teq)4]Sredk :=l((redk2) k2- ODtube Aeq = 1.96 in 2 Seq = 6.44 in 3 S red'6.01 5.87 5.71 5.52 5.30 5.01 1.16.3 in Smin:= min(Sred)Smin= 1.16in 3 A stress multiplier is used for the core tube. This stress multiplier is applied to the GTSTRUDL results (which is based on the equivalent thickness) to account for the largest core tube holes. This multiplier is, Kct:= eq Kct = 5.54 Smin I Page: 45 of 107 Calc. No.: PCI-5464-SO1 Revision:

2 Client: Performance Contracting Inc.Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes W No D Date: 08/25/06 Edge Channel Properties This section calculates the edge channel properties (i.e. effective cross-sectional properties) including the combined effect of the perforated plate disks that are riveted to the channels (also made from perforated plate).The channel and the attached perforated plate work as a combined section to resist bending loads. The effective width of the perforated plate that acts in combination with the radial stiffener is based on Section 2.3 of the ASCE Standard (Reference

[221) which provides design guidelines for very thin members such as the perforated plate.The effective width of the plate is limited by the width to thickness ratios such that local buckling of the plate will not occur for the compression face. The combined properties are used to solve for an effective channel shape that has the same properties, and this effective channel shape is used in the GTSTRUDL model.The width of the disk face that is effective in the Ych y combined section is based on the ASCE Standard (Reference

[22]). The slenderness factor, X, is b1 determined from Equation 2.2.1-4 of Reference eff[22]. Conservatively consider the face disks to be unstiffened elements with a total width equal to the distance from the edge of the disk to the edge of the hole for the core tube. Note that this conservatism more than offsets any impact resulting from the connection of the perf plate to z z the channel not being continuous dchan e The ligament efficiency (hip) for the perforated PC _ _ _plate is hdisk.holes h bchan hp .p=04 Pdisk.holes h From Fig.A-81 31-1 of Reference

[4], Figure 6.4-6 -Combined.

Channel and Plate Section Effective Poisson's ratio, veff 0.325 Effective Modulus of Elasticity, Eeff 0.39. Esa Eeff = 10784 ksi min(Lldisk, L2disk)-Lcirc.in 1.052 2 Sya x := X = 8.06%O50tperf Eeff

_ 1Automated Engineering CALCULATION SHEET Page: 46 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes W No D Date: 08/25/06 The effective width is determined from Equation 2.2.1-5 or 2.2.1-6 of Reference

[221 fif .7 (min(L1 disk, L2disk) -Lcirc.in 9\ min(L disk, L2disk) -Lcirc.in beff := ;L < 0 6 7 3 ,y 2 ' x ' 2 beff = 0.80 in Using this effective width, the properties for the combined section are determined.

Note the properties are based on solid sections (no perforations).

The equivalent modulus is used in the GTSTRUDL model to account for stiffness, and the Kpp factor is applied later to calculate the stresses considering the holes.Ach.x := [2.beff + 2.bchan + (dchan tperf)]-.tperf beff 2+ bchan 2+ (dchan -2'tperf)'(t -r Ach.x = 0.17737 in 2 Ych = 0.302 in Ych :: 2.beff + 2.bchan + (dchan -2.tperf)(beff)-(dchan

+ 2-tperf)3 (beff -bchan)-(dchan3)

Ich.z 12 12 (bchan -tperf).(dchan 2 .tperf)3 12 (dchan -2"tperf)'(tperf) rf)-( tperf Ych-ly =122 ntperf 2 bchan )fbchan ly2:= 2. 1- + tperf bchan" Ych -" Ich.z = 0.0107 in4 lyl = 0.0017 in 4 ly2 = 0.0014in 4 ly3 = 0.0060 in 4 Ich.y = 0.0091 in4 ly3:= 2.12 + tperf *beff yYch -rpr~b ~ be2 ) 2]1 ch.y= (lii + 'y2~ + y3)

Automated Engineering CALCULATION SHEET Page: 47 of 107 Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes No D Date: 08/25/06/ Ich.z Rch l : Ach.x Ich.y Sch'y := beff -Ych' ch.y Rch.y := Ac Ach.x Ich.z S ch.z := c a dchan 2 + tperf 2 Rch.z = 0.245 in Rch.y = 0.226 in Sch.y = 0.0182 in3 Sch.z = 0.0344 in3 A solve block is used to calculate a channel cross section that has section properties equivalent to those calculated above. Before entering the solve block, initial guesses must be made for all variables and the units must be removed.Initial Guesses: Lfllange I beff + bchan Lflange " 2.in tperf tweb .in Ach.x Ach ..2 in Ich.z'ch.z:=.4 in dchan + tperf Lweb: -in tperf tflange'-

in Ych Ych.eff : -in lch.y -- Ich.y.4 in L-Iweb--tweb tflange Schy: Sch.y Figure 6.5-7 -Effective Channel used in STRUDL.3 in Automated Engineering CALCULATION SHEET Page: 48 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes l No D Date: 08/25/06 Given Ach = 2.Lflangeitflange

+ (Lweb -2.tflange).tweb tflangeanflange 3 Lweb- tflange" 2 1ch.z `2 12 + 2Lflangeflane 2 2 tweb2 (Lflange2"tflange)

+ (Lweb- 2-tflange)-(Lweb 7 2tflange)3tweb Ych.eff =2.Lflange tflange + (Lweb -2.tflange).tweb F t1an1 (Lflan ge Ich.y = 2. 12 + Lflange tflange" " -Ych.eff,,2j 1+ -tf an e) we +/-(Lw eb -2 ( -tw eb -2 1Le-2"tlne'wb

+ (Lweb -2"-tflange)'-tweb'

(--- -Ych.eff I Sch.y I= ch.y Lflange -Ych.eff Find(Lweb, tweb, Lflange, tflange, Ych.eff) =0o.655 " 0.139 0.750 0.071 ,0.252 Back checking against the section properties calculated above with those calculated by GTSTRUDL using the flange and web lengths and thicknesses from the solve block, the effective channel is verified and acceptable for use in the GTSTRUDL model.MEMBER/SEG TYPE SEG.L AX AY AZ IX IY IZ SY SZ"" YD ZD YC ZC EY EZ""EC100I TABLE MYCHAN WBCHANEF 0.178 0.091 0.071 0.001 0.009 0.011 0.018 0.033" 0.655 0.750 0.327 0.252 0.000" U Automated Engineering CALCULATION SHEET Page: 49 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes El No L] Date: 08/25/06 6.4.3 Member End Releases The actual configuration of the connections is modeled by adding member end releases to the model. The following releases are used in the model: The moments for tension rods are released at their ends where they attach to the welded radial stiffeners.

The moments on the edge channels are released where they connect to the tension rods.The spacers are released at the ends where they attach to the welded radial stiffeners.

They are attached to the rest of the model only at these locations, as the joints in between are created through the use of the JOINT TIES and SLAVE RELEASES commands.

The coincident nodes for the spacers and the tension rods are initially tied together for all degrees of freedom, then slave releases are used to release the relative axial displacement, and the relative torsional rotation, and the relative lateral rotations at all of the intermediate nodes (Fx, Mx, My, and Mz). For the end nodes, where the spacers attach to the radial stiffeners, all of the moments are released (Mx, My and Mz). These nodal relationships are verified by examining the nodal displacements at these locations and confirming the command is working as intended.The cables are released at their ends at the top comers where they connect to the radial stiffeners, and also at the bottom corners. A detailed discussion on the cable end releases is provided in Section 6.4.1.The core tube rigid links are released for Mz at the connection with the collar as this weld cannot transfer moments. Also the rigid links used to connect the hex couplings between modules are released for all three moments. Note these are fictitious members and do not take any loads.For downward vertical load cases (DW, DEB and PRES), the core tube to core tube sleeves are released at one end for force Fy & Fz, and moments Mx, My, & Mz. For other load cases, the Fx force is also released (sleeve can not take tension).6.4.4 Support Joints and Joint Releases The 4 strainer module stack (one 7 disk module and three 6 disk modules) is supported at the corner support joints. All three moments are released at these support locations as this is a bolted connection which is considered pinned. The flexibility of the supporting plenum structure is considered by modeling springs at these four support nodes to represent the stiffness of the plenum. The spring stiffnesses are calculated on the next page.Note that the hex coupling joints at the intersection between the first and second modules (Joints 201 to 204)are fixed for the X2, Y2, MY2, and MZ2 load cases only. This is used to determine the flexibility of a single 6 disk strainer module. These joints are fully released for all other load cases.Joint 1000 at the bottom of the core tube for the bottom module is supported with spring support in the vertical direction for vertical downward load cases (DW, DEB, and PRES). All moments and Fx & Fz shears are released.

A spring stiffness is input in the vertical direction equal to the average stiffness of the four comers calculated on the next page. This spring stiffness represents the flexibility of the plenum. Note that this joint is released for all other load cases.

U/ Automated Engineering CALCULATION SHEET Page: 50 of 107 Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 Plenum Stiffness The flexibility of the supporting plenum structure is input into the GTSTRUDL model using spring supports.

The stiffness of the spring supports is calculated from the results of the GTSTRUDL run for the plenum included in Reference

[14]. Several stiffness load cases are run in the plenum model as follows: STIFFX -1000 lbf unit load is applied in the X-direction at every strainer module node simultaneously STIFFZ -1000 lbf unit load is applied in the Z-direction at every strainer module node simultaneously AEY -1000 Ibf unit load is applied in the Y-direction at Node AE1 BEY -1000 lbf unit load is applied in the Y-direction at Node BE1 AEY1 -AEY4 -250 lbf per node is applied at the four corner nodes for Module AE STIFFX is used to determine the stiffness in the X-direction.

This is the most flexible direction due to the flexibility of the support beam webs. The maximum displacement at any strainer center node is at Node AA1 and is 0.073 inches. Therefore the stiffness of the four support points is calculated as follows: 1000.1bf KFX:=4.0.073 .in KFX= 3.4x 10 bf in Similarly, in the Z-directions, the maximum displacement is at Node CE1 and is 0.0075 inches.1000.lbf KFZ:.4.0.0075.in KFZ=3.3x 104 lbf in (Note 3.4E4 used in the model, small difference OK)In the Y-direction, strainers AE and BE were chosen due to the fact that these strainers are over the pit and the supporting structure is more flexible due to the flexibility of the beams that span the pit. Also reviewing the plenum model, Strainer Module AE has the biggest displacement and is influenced by having stiff supports on one corner and more flexible supports on the other corners. Based on review of the results, the stiffness of the AE module corners was chosen as the worst case. Based on the displacements from Reference

[14], the stiffness of the four corners is taken as: 250.lbf KFY1 :=-0.000025 .in 250.lbf KFY2 -0.00011 -in 250-lbf KFY3 -0.00011 -in 250.lbf KFY4 -0.00068 in KFY1 = l.Ox 10? 7bf in KFY2 = 2.3 x 106 lf in KFY3 =2.3 x 106 bf in KFY4 = 3.7 x 105 lbf in (Load AEY1, Node SR7)(Load AEY2, Node SR8)(Load AEY3, Node SR21)(Load AEY4, Node SR22)Note slightly different values are used in the GTSTRUDL analysis.

The difference is negligible Automated Engineering CALCULATION SHEET Page: 51 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers IReviewed By: Kishore D. Patel Safety Related Yes -No -Date: 08/25/06 6.4.5 Member Density Adjustments The densities for some of the members are adjusted to account for the weight of the strainer components which are not directly included in the model. The disk faces, the intemal wire stiffeners, and the gap disks are not directly included in the model, therefore the density of the edge channels and the tension rods are manually adjusted to account for this additional weight. A check of the total deadweight reactions from GTSTRUDL is used to confirm that the total deadweight included in the GTSTRUDL model is dose to the total weight calculated in Section 6.1. The weight of the debris is also included in the density calculations for Load Combination

1 & 5.For these components, a portion of the weight is tributary to the inner rods (Group 'I ROD'), and a portion is tributary to the outer channels (Group 'CHANNELS') (which in turn are supported by the outer rods). The inner rods support the perforated plate through the spacers. The percentage breakdown for how much weight is tributary to the inner rods, and how much is tributary to the outer edge channels will be based on the formulas from Case 2c of Table 24 of Roark and Young, Reference

[16].An equivalent outer radius "a" is determined based on a equivalent area L1 disk.L 2 disk a:=J 7 a= 15.80 in q:= Ipsi ODgap 2 b = 7.87 in ro := b 3 Eeff'tperf 12.(1 -Veff)C1.I +2 a lb ft 2 D = 567.46-2 sec veff a+ 4 (b a)C3:= -( -2 ]." a +1b)4.a a b)_C7 := 1.(I1- vef2)-.(a

_ b)C 9 := b .-In ( ) + 1ef [ _- b a b 4 kay

< Automated Engineering CALCULATION SHEET Page: 52 of 107 L Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 ,o 2 r ) ro 2 [ ro ) ] , ( a Lll:=-[ 1 + 4.- -5.- -4 _2 +64 (1 ae..a a L17:='[ -I I -Ii)] -1[+ (I + veff)+.rno-]

Using these coefficients, the reaction at the inner circle is determined as a percentage of the total pressure load.C 1 "L 1 7-C 7--1 1 Q:=q.a. 1g-Q:qa.C1 .C9 -C3.C7 Qb.(2.7 .b)Ktube:-q .(a b b2 )lbf Qb = 5.11-in Ktube = 0.43 Using this ratio, the total masses in the vertical direction are distributed to the inner rods and to the outer channels U Automated Engineering CALCULATION SHEET Page: 53 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes W No D Date: 08/25/06 Tension Rods The total length of the tension rods in the GTSTRUDL model goes from the centerline of the radial stiffener on one end, to the centerline of the radial stiffener on the other end. This length is broken up into two lengths, one for the middle section of the rods that is unthreaded, and another for the ends of the rods which are threaded.Note the rod ends are modeled with a smaller diameter to account for the reduction due to the threads. The rod lengths are calculated below: Lrod.gt := Lstrnr -(Wdisk)Lrod.end.gt

= Wdisk + tstfnr Lrod.gt = 9.7 in The total volume of the inner rods is It 2 Nrod VOLrod.gt:=

4"-ODrod 'Lrod.gt' 2 7E 2 Nrod VOLrod.end.gt:=

--ODtens *Lrod.end.gt' 2 42 Lrod.end.gt 0.87 in ( 6.36 in 3 VOLrod'gt

= (7.63)VOLrod.end.gt

= 0.49 in 3 Adding in the weight of the wire stiffeners, the face disks, and the gap disks to determine an equivalent density for the inner rods. In addition, the weight of the debris is added as well. Two load cases are considered, one that includes the weight of debris (Load Combination

1 & 5) and one that does not (Load Combinations

2, 3, 4, & 6).Prod.0:=Prod.1 :=0.5.Wtrod

+ Wtgap + Ktube.(Wtface

+ Wtradial + Wtcirc + WD)VOLrod.gt

+ VOLrod.end.gt 0.5.Wtrod

+ Wtgap + Ktube.(Wtface

+ Wtradial + Wtcirc)VOLrod.gt

+ VOLrod.end.gt (24.99 lbf' ý24.65 in3_(8.78 ) lbf r k8.64J in 3 Conservatively, the maximum density for either the 7 disk or 6 disk modules will be used for all members since the differences are small. Also slightly higher values were used in the model than those shown above. The differences are negligible.

_ Automated Engineering CALCULATION SHEET Page: 54 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No N Date: 08/25/06 Edgqe Channels Similarly, the length and volume of the edge channels needs to be determined Lch.gt := 2.Ll circ.out + 2.L 2 circ.out VOLch.gt:=

Ach.x"Lch.gt'Ndisk Lch.gt = 104.50 in VOLch.gt = 112) in3 Adding in the weight of the wire stiffeners and the face disks and debris to determine an equivalent density for the edge channels (note the gap disk weight is placed entirely on the inner rods), Wtedge + (1 -Ktube).(Wtface

+ Wtradial + Wtcirc + WD)Pch.0 Pch.1 VOLch.gt Wtedge + (1 -Ktube).(Wtface

+ Wtradial + Wtcirc)Pch.0 Ibf (c .in 3 1 = (0.759 Ibf Pc.1(0.759 Jin 3 (0.10) lbf Pch.2= = l -(~0.10 -in 3 VOLch.gt Wtedge Pch.2 .-VOLch.gt Conservatively, the maximum density for either the 7 disk or 6 disk modules will be used for all members since the differences are small 6.4.6 Member Added Inertia The mass of the internal wire stiffeners, disk faces, and gap disks are added via the MEMBER ADDED INERTIA command for the seismic analysis rather than adjusting the density. This is done because the direction of motion affects where the weights are being applied. In the vertical direction, the weights of the stiffener wires and the face and gap disks are considered to be carded by the edge channels and the inner tension rods (proportioned in the manner as for the densities in section 6.4.5). In both the lateral directions however, these weights are carded only by the tension rods. Note that the densities calculated in Section 6.4.5 above are used only for non seismic loadings such as the gravity load case. For the seismic case, standard steel density is used.End Cover Mass The weight of the end cover is included by inputting a member added inertia for the rigid links that connect the radial stiffeners to the end of the core tube. Only the members at the top of the core tube for the top module have an end cover. These rigid links are Members 'RIGID29' to 'RIGID32' and have a total length of 26.5 inches.

I Page: 55 of 107 Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes El No D Date: 08/25/06 Wtec 8ec .-26.5 .in lbf 5ec = 0.305 -in Disk Mass Vertical Direction Apply to edge channels: 5iky (I -Ktube) (Wttace + VWtradia, + VWtcirc)ds:LNdisk Lch.gt )Apply to inner rods: d0.y12 )bf (0s'y .12J in 8inner.y `(inry 1.59 1 in Nrod* .(Lrod.gt

+ Lrod.end.gt) 2 X Horizontal Direction Apply to all rods: 5rod.x ~Wtface + Wtgap + Wtradial + Wtcirc Nrod'(Lrod.gt

+ Lrod.end.gt)

I 5rod~x r182 Z Horizontal Direction Apply to all rods: Wtface + Wtgap + Wtradial + Wtcirc 6 rod.z :: 1.82) rbf (rd~= 1.80J in Nrod.(Lrod.gt

+ Lrod.end.gt)

Plenum Mass A portion of the mass of the plenum is included in the four stack model on Members 'ELMNT17' to 'ELMNT20'.

These members are the "rigid links" at the very bottom of the model connecting the four elastic support points.The magnitude of the mass was determined by trail and error during the benchmarking process in order to get a good match on the frequencies and mode shapes between the four stack model and the plenum model analyzed in Reference

[14].

_1M Automated Engineering CALCULATION SHEET Page: 56 of 107 Services Corp Calc. No.: PCI-5464-S01 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes Wl No D Date: 08/25/06 6.4.7 Tension Rod Preload The tension rods and spacers are preloaded by torquing the rods. This preload is included in the GTSTRUDL model by inducing a negative temperature change on the tension rods. This makes the rods get shorter, while the spacers stay the same length, causing the rods to go into tension, and the spacers to go into compression.

The core tube, cross bracing, and two of the module support nodes are released in the axial direction for the temperature load case such that these members do not pick up the compression as opposed to the spacers. This will be assured in the fabrication of the strainers by torquing down the tension rods before welding the top radial stiffener to the core tube and before securing the cross bracing to the welded radials. The magnitude of the negative temperature changes are calculated below.The amount of the preload force is determined from the torque to preload conversion formula given in Good Bolting Practices (Reference

[15]). Per Reference

[15], use a nominal nut factor of 0.3 for stainless steel fasteners.

Conservatively consider a 20% variation in the torque to preload conversion due to uncertainty.

Also consider the possible variation in torque due to torquing tolerance (15%). In addition, preload relaxation is considered in the qualification of the spacers in Section 6.5. These uncertainties will be applied in the worst case combination (maximize the preload in the GTSTRUDL run to get the highest stresses, and minimize the preload when checking for separation in the spacers).Knf := 0.3 Trod. I. 15.1.2 0 Fload.max:=

ODrod.(Knf)

Fload.max

= 3864 lbf Other parameters needed for this analysis include CTE = 8.77 x 10- 6 7E 2 Arod= -OlDrod 4 Arod = 0.20 in 2 71 2 Aend.rod := --ODtens 4 Aspcr:= 4-.(ODspacer

.2 Aend~rod =0.l 4 in IDspacer2)

Aspcr = 0.32 in2 I Page: 57 of 107 Caic. No.: PCI-5464-SO1 Haunt- P~rfnrninný rnntrcir;nn Ton'Pavikinne I Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 To calculate the temperature change required to induce the desired preload force on the rods and spacers, the amount of deflection for the spacers due to the temperature change must equal that of the total length of rod (middle section and end section at the threads).espcr= "A.E .F1 + 0, I"ATILI erod= A.E F2+ 2AT2L2 eend.rod = A.E3F3 + (3.AT 3 L 3 (deflection of spacers)(deflection of middle of rods)(deflection of ends of rods)0, = (X2 = (-3 = CTE Solving first for espcr by setting AT 1 to zero and F 1 equal to the preload force, noting that Fload will be a compressive force for the spacers.Lstrnr + tstfnr espcr:='(-Fload~max)

-0.0039/espcr =-0.0046 in-0.0046)4-(ODspacer2-IDspacer2)

.Esa Now solve for the required temperature change for the tension rods by setting the change in length for both the middle of the rod and the ends of the rod equal to the change in length of the spacers. For simplicity, assume that the temperature changes for both the rod middle and ends are equal.erod + eend.rod = espcr Solving the above equation for AT, ( Lrod.gt Lrod.end.gt espcr -Fload.max

-+eArod'Esa Aend.rod'Esa)

CTE.(Lrod.gt

+ Lrod.end.gt)

AT:=This value is confirmed AT (134 ) degrees F by reviewing the actual T -133.5 resulting preload from the GTSTRUDL results U Automated Engineering CALCULATION SHEET Page: 58 of 107 Services Corp Calc. No.: PCI-5464-S01 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No Eli Date: 08/25/06 6.4.7 Effective Length Coefficients The effective length is automatically calculated by GTSTRUDL as the node to node length for each member. In special circumstances where intermediate nodes have been used for a collective member, effective lengths were manually inputted.

This is done for the edge channels, external radial stiffeners, and the seismic stiffeners.

In addition to the effective length adjustments described above, the effective length factors in GTSTRUDL are used to account for stainless steel in place of standard carbon steel. An equivalent K-value must be computed to adjust the GTSTRUDL code check equations for the edge channels and the external radial stiffeners.

The ANSI/AISC N690 code (Ref. [21]) provides equations for stainless steels and carbon steels (the latter being employed by GTSTRUDL).

Upon further examination, only the compression equations are of interest.

In order to force the GTSTRUDL allowables for carbon steel to reflect the allowables for stainless steel, a effective K-value is computed and inputted into GTSTRUDL.i:= 1.. 2 Eeff El := Esa)Sy~az -Sya S kse (10784 ) ksi k27650)E for Edge Channels E for External Radial Stiffeners Sy.a 25.50 Keq = C 1.00)Edge Channels External Radial Stiffeners.

LLa 1Lcirc.out2

+ C2circ.out 2 ODdebris 2 k L2circ.out Lklr :=(, Lrad SRch.z" rklr := tstfnr Keq" Lklr KLR.-rklr Lrad= 10.85 in (26.12)LkIr = I10.2 ) in rklr 0.0722 in (external radial stiffener unbraced length)(Note these unbraced length are also inputted into GTSTRUDL)Note r for a rectangular section reduces down to equal to the thickness divided by the square root of 12.KLR = (106.6)\150.3J U Automated Engineering CALCULATION SHEET Page: 59 of 107> l Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes [Z No D Date: 08/25/06 The allowable compression stress in accordance with N690 (Reference

[21 ]) for each of these members is: Sy.a Fa.ssl.-1 2.15-Sy.a 25 -6 Keqi

Lklr, 120 rklr.I1 Keqi Lklri x Fa.ss2i := Sy.a[ 0.40 -60 e" klr]Fa.ss : if(KLRi < 120, Fa.ssli, Fa.ss2i)C 6.655)Fa'ssi = ,.1 (4.5191 Fa.ss2 = 3.8 6J Fa 'ss = 6.66)(Q1.5-11 )(Q1.5-12 from Supplement 1)GTSTRUDL calculates the compression allowable dependent on the value of Cc. If you consider that KL/R exactly equals Cc, the GTSTRUDL would calculate the compression allowable as: S -.a Fa.cc .-53 1 38 8 Fa.cc = 6.652 (For KLJR = Cc)The Cc and the L/R ratio for the affected members are: 2 2i 2.2E 1 Cc:= ya C 91.36 C 146.30 (Reference

[21 ])L-kir C 106.6)LRklr := rklr LRklr = 150.3 rklr 15 .3 If you consider that the effective KL/r in GTSTRUDL ends up being less than Cc, then the effective K value can be solved for by setting the GTSTRUDL equation equal to the actual compression allowable per N-690.KaCS1 := I (initial guess)

_ l Automated Engineering CALCULATION SHEET Page: 60 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 (KaCS1VLRkIr)~

KaCS1 := root I Fa.ss., KaCS1 I= 0.857 KaCS1 = 1.165)5 3 3 ( (KaCS1 LRklr i) ((KaCSi LRklrj)*8 (Cc)3 If you consider that the effective KL/r in GTSTRUDL ends up being greater than Cc, then the effective K value can be solved for by setting the GTSTRUDL equation equal to the actual compression allowable per N-690.2 El ksi KaCS2:= 2--.2 F a'ss 2 3"LRklr C 0.857)KaCS2 = \1.286 The applicable equation can be determined by comparing the N690 allowable to the GTSTRUDL allowable based on KL/R equal to Cc. Therefore, the effective length factor to use in GTSTRUDL is: KaCSi :: if(Fa.ssi

< Fa.cc, KaCS2 i, KaCSli)0.857)KaCS = C,1.286)Kz Edge Channels Ky External Radial Stiffeners In addition to the equations for the allowable compression stress, N-690 also provides a lower allowable for Fe'.Equating the equation for Fe' of carbon steel to austenitic stainless steel and solving for the K-value of carbon steel, K 12.(2. 15) .Keq 2 KeCS := 23 (1.06 )KeCS = 1.06 The effective K value to be used in GTSTRUDL is the maximum between these two values. Using the maximum between the two will provide a conservative result. These are the values input into GTSTRUDL.

If the members fail the GTSTRUDL code check a detailed calculation can be performed.

Keff := max(KaCSi, KeCS i)Keff = 1.06)(1.29 Kz Edge Channels Ky Extemal Radial Stiffeners Automated Engineering CALCULATION SHEET Page: 61 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes Q No ED Date: 08/25/06 6.4.8 Loads and Load Combinations The following load cases are applied in the GTSTRUDL model Load Name Description WT Dead Weight of the Strainers PRELOAD Temperature change used to induce preload into the tension rods WT + DEB Dead Weight of the Strainers

+ Debris weight PRESSURE Unbalanced pressure load on strainer end cap RSOBEX, RSOBEY,RSOBEY2 RSSSEX, RSSSEY,RSSEY2 MMOBEX, MMOBEY,MMOBEY2 MMSSEX, MMSSEY,MMSSEY2 Response spectra loads for OBE in the X-direction and Y-directions Response spectra loads for SSE in the X-direction and Y-directions Missing mass load (ZPA) for OBE loads in the X-direction and Y-directions Missing mass load (ZPA) for SSE loads in the X-direction and Y-directions Note: Load cases with "Y" only are based on all cables being released, and load cases with "Y2" are based on all cables being active. Load cases with "X" have only X-tension cables active.Loadingq For Stiffness Matrix and Benchmarkinq CABLE X1, Y1, MYl, MZ1 X2, Y2, MY2, MZ2 X2, Y2, MY2, MZ2 BENCHX Static lateral load used to determine which cables are in compression Loads used to determine flexibility of 7 disk pinned module (used in plenum calc)Loads used to determine flexibility of 6 disk fixed module (used in plenum calc)Load used to determine flexibility of 7 disk fixed module (used in plenum calc)Load used for benchmarking the x-displacement (used in plenum calc)

U/I AutomatedEngineering CALCULATION SHEET Page: 62 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes No D- Date: 08/25/06 Load Combinations:

Following load combinations are created for the code check.DW Steel weight + Preload DW+DEB+P Steel weight + Debris weight + Preload + Pressure SEISOBE, SEISOBE2 OBEX + OBEY and OBEX + OBEY2 SEISSSE, SEISSSE2 SSEX + SSEY and SSEX + SSEY2 DW+OBE+, DW+OBE2+ DW + SEISOBE and DW + SEISOBE2 DW+SSE+, DW+SSE2+ DW + SEISSSE and DW + SEISSSE2 DW+OBE-, DW+OBE2- DW -SEISOBE and DW -SEISOBE2 DW+SSE-, DW+SSE2- DW -SEISSSE and DW -SEISSSE2 Note: Load combinations with "2" are based on all cables being active for the Y-earthquake.

Load combinations without a "2" have all cables released for the Y-earthquake.

For the X-earthquake, only tension cables are active.

_ Automated Engineering CALCULATION SHEET Page: 63 of 107 jJ' Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No Date: 08/25/06 6.5 GTSTRUDL Results The results from the GTSTRUDL run are provided below. GTSTRUDL performs a code check of all of the members for both the OBE and SSE load combinations.

The results of the code checks are summarized below: Compone nt Welded Radial Stiffeners (including Collar)Tension Rods Edge Channels Cross Bracing Cables Hex Couplings Core Tube (including Core Tube Sleeves)Interaction Ratio ( 0.24 0.70 lRstfnr := 1.02 r + CTrect L 0.46 0.46 IRrod :=0.54 1 + CT)0.29 Kpp IRchan := 02-p 0.40.Kpp I+ CT)0.0 0.30 IRcable :=0.53C+ CT, 0.19 0.28 IRhex:=0.39 I + CT, (0.033 Kct 0.019.Kct IRtube :=0.032- Kct I.+ CT)Load Comb.DW+DEB+P DW+OBE DW+SSE DW+DEB+P DW+OBE DW+SSE DW+DEB+P DW+OBE DW+SSE DW+DEB+P DW+OBE DW+SSE DW+DEB+P DW+OBE DW+SSE DW+DEB+P DW+OBE DW+SSE Member No.COL1 COL8 COL8 IROD108 IROD108 OROD708 EC1002 EC1002 EC1002 N/A CABLE5 CABLE5 HEX3 HEX2 HEX4 CT1 CT1 CT1 Summary"0.24 " IRstfnr= 0.70 ,0.85 (0.46 IRrod = 0.46 K0.42"0.51 " IRchan =0.73 o0.78o" IRcable 0.30 f0.19" I Rhex = 0.28 0.30IRtube = 0.11 ,0.14 j I I Page: 64 of 107 Calc. No.: PCI-5464-S01 Hante ID vf-- 1"-frantin Inn fawiicnn-I Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 Component Bent up Portions of Radial Stiffeners Interaction Ratio 0.06 0.19 lRbent:= 0.3 0.33 I + CTrect L 0.80 0.86 IRspcr 0.98 I + CTrect Load Comb.DW+DEB+P DW+OBE DW+SSE DW+DEB+P DW+OBE DW+SSE Member No. Summary BENT1 PA6 PA6 I0.06"[Rbent= 10.19 0..28, I Spacers SPCR502 s 0.80j SPCR602 IRspcr = 0.86 SPCR602 I Spacers The spacers are qualified by comparing the maximum stresses due to seismic, with the initial compression load.As long as the seismic stress is less than the preload (with an allowance for relaxation in preload over time), then the spacers will always be in compression.

If the extreme fiber seismic stress were to exceed the prestress, then there is the potential for a gap to open at one of the splices (because the spacers can not take tension because they are not continuous).

However, in this case, this does not constitute a failure of the strainer, this just represents the maximum linear elastic capacity of the spacers. In this case any additional load is taken solely by the tension rods.The reduction in preload due to relaxation is based on Reference

[26]. As per Section 4.4 of Reference

[26], an average loss of about 5% of the preload can be considered to occur immediately upon completion of the torquing.

An additional relaxation of about 6% typically occurs over the long term. Relaxation is expected to increase with grip length. See these tension rods have a very long grip length, with many connected spacers additional relaxation beyond these values may result. Therefore 15% relaxation is conservatively considered (about 40% increase over the standard industry relaxation of 11%). Note that since the normal operating temperature of the strainers is moderate (less than 140 degrees), additional creep associated with high temperature service need not be considered.

In addition, uncertainty in the applied bolt torque and the torque to preload conversion is considered to account for minimum possible preload.cyspcr.seisl cyspcr.seis2 1183 + 602.in.lbf 0.048 -in 3 3878-lbf -3863.lbf+Aspcr Max moment on the spacers [Member'SPCR503' or SPCR707 per Attachment B]divided by the section modulus from GTSTRUDL plus induced tension divided by area./161 + 97 .in.lbf 3878.lbf -3754.lbf 0 +0.048 .in3 Aspcr uspcr.seis=

max(cGspcr~seisl , uspcr.seis2) scse =40pi cyspcr.seis

ý 4303 psi

_I Automated Engineering CALCULATION SHEET Page: 65 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes N No D Date: 08/25/06 The minimum preload in the spacer is Trod-0.85.0.80.0.85 Fload.min

= ODrod.(Knf)

Fload.min

= 1618.4 lbf cspcr.pre

= 5057 psi (0.85 for under torque tolerance)

(0.80 for torque to preload conversion uncertainty (0.85 for preload relaxation)

Fload.min cyspcr.pre

.-Aspcr IRspcr.s -cyspcr.pre IRspcr.s = 0.85 (Conservative) 6.6 Disk Pressure Loads Loads are applied to the strainer disk faces depending on the type of load. Seismic loads are applied in proportion to the tributary mass acting on each strainer component.

These tributary masses are calculated in Section 6.4.Differential pressure loads act across the perforated plate and attempt to collapse the strainer during operation.

The differential pressure is based on the worst case head loss through the debris covered strainer.The pressure loads on the strainer is broken down into the various strainer components, or surfaces.

The break down is as follows: End Disk -The outside faces of the end disks.Middle Disk -The faces of the interior, or middle disks.End Cover -The plate covering the very end of the core tube.Outer Rim -The perforated plate webs of the edge channels at the outside diameter of the disk Inner Gap -The curved inner gap perforated plate in between disks.Axial loads are applied to the end disks, the middle disks, and the core tube end cap. Vertical and lateral loads are applied to the outer rim and inner gap perforated plates.

_ / Automated Engineering CALCULATION SHEET Page: 66 of 107 u Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 6.6.1 Axial Loads The equivalent pressure acting on each disk face is determined by multiplying the accelerations by the tributary volume (or mass). The mass takes into account the weight of the steel, the weight of the debris. Two load combinations are examined, Load Combination

0 (DW + DP + DEB), and Load Combination

2 (DW + SSE).End Disk Face (controls over first disk and inner faces of end disks)qend.disk.0

= DP + Ltperf'PRdisk'Psteel

+ maxWDs qend.disk.0

= 1.56 psi Wtradiall

+ Wtcirc]*I + 1.5.av2)Ndisk1 "(LI disk" L 2 disk 7E 4 qend.disk.2

0.035 psi Middle Disk Face qmid.disk.0:

DP +tperf.PRdisk.Psteel

+ max WD).As J qmid.disk.0

= 1.56 psi Wtradial1

+ Wtcirc, qmid.disk.2:=-I+ 1.5.av2)qmid.disk.2

= 0.035 psi Page: 67 of 107 Caic. No.: PCI-5464-S01 T) lint nfnr T"o i r~ n Udo-wicnne I, tSJS flit* ,LUI f l flUlaJlA.~

..AflItI a.LI .I 111'.,* .V 103S1S* 4ll .Jl , Station: Watts Bar Unit I Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 Core Tube End Cover (End Core)qend.core.o:-

DP + te Prdisk Psteel +max cAs)qend.core.2

= tperf'PRdisk'Psteel' ( I÷ 1.5'av 2)qend.core.0

= 1.56 psi qend.core.2

= 0.011 psi 6.6.2 Lateral Loads Lateral loads are determined similarly to the axial loads calculated above. Lateral loads are split into two components, loads acting on the edge channels, and loads acting on the inner gaps. Similarto axial loads, for acceleration loads, the portion acting on each component is based on the tributary water volume acting on each segment. Also, applied pressures are divided by two as 1/2 is applied as a positive pressure to the front face, and 1/2 is applied as a negative pressure on the back face.Ed-ge Channel qchan.O := DP qchan.0 = 1.52 psi qchan.2 = 0.005 psi qchan.2 := ( Wtedge

1.5.ah' Ndisk.2.Ldisk.Lldisk) 2 Inner Gap qgap.O:= DP qgap.0 = 1.52 psi S Wtgap 1 qgap.2:=

1.5.ah2\Lgap I *2"ODgap )qgap.2 = 0.023 psi Automated Engineering CALCULATION SHEET Page: 68 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E- No D Date: 08/25/06 6.6.3 Disk Pressure Summary Mid ITy Outer Disk cdle Disk aP]ap-0~~0 iLl (,01 Inner G End Disk ,z_zzz Core Tube Z End Core Figure 6.6-1 Disk Face Pressure Summary Surface 1, End Core Surface 2, End Disk Surface 3, Middle Disk Surface 4, Edge Channel (Lateral)Surface 5, Inner Gap (Lateral)Operatingq Conditions qend.core.0

= 1.56 psi qend.disk.0

= 1.56 psi qmid.disk.0

= 1.56 psi qchan.0 = 1.52 psi qgap.0 = 1.52 psi Seismic Conditions (SSE)qend.core.2

= 0.011 psi qend.disk.2

= 0.035 psi qmid.disk.2

= 0.035 psi qchan.2 = 0.005 psi qgap.2 = 0.023 psi Page: 69 of 107 Calc. No.: PCI-5464-SO1 Revision:

2 Client: Performance Contracting Inc.Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E- No D Date: 08/25/06 6.7 Perforated Plate Evaluation The perforated plate is analyzed as an equivalent solid plate. The thickness used is the actual thickness, however an equivalent Modulus of Elasticity and Poison's ratio is used to account for the holes from a stiffress perspective.

When determining stresses however, the stresses need to be factored up to account for the holes in the plate. Article A-8000 of the ASME B&PV Code (Reference (41) is used to determine the actual stresses in the perforated plate using the results from an equivalent solid plate analysis.

Note that this perforated plate does not meet the thickness limitation of A-81 10 (a)(5), however per Reference

[19] (which is the paper from which A-8000 is based) this limitation was associated with the figures provided for the equivalent elastic modulus and Poisson's ratio and therefore does not impact the stress equations given in A-8000.A-8142.1 provides the following equations:

2 W 2 h = P -. + V L) + Ur'bar 2<Sm h t n--S= K.--. ave <1.5 Sm Where: Sm = ASME allowable stress intensity K = Stress multiplier to convert principal stress into stress intensity (from Fig. A-8142-1)P = Pitch (spacing) between holes h = Ligament width between holes Gave = Maximum principal stress (larger of radial or tangential)

These two equations are basically the membrane and membrane plus bending checks for the plate: The term under the radical for the first equation is just the formula used for a circular perforated plate to calculate the membrane stress by hand. The K factor is a function of the biaxiality ratio (ratio of orr to cr 0) and is just used to convert the maximum principal stress to the maximum stress intensity.

To determine this factor, a closer inspection of Figure A-8142-1 from Article A-8000 is required.

Since this strainer is considered a Class II component, stress intensities are not calculated and only the maximum principal stresses are considered.

Therefore the K factor is not applied. The allowable stress is taken as 1.5 S as per Reference

[29].

U' Automated Engineering CALCULATION SHEET Page: 70 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 The stresses in the perforated plate are examined at five locations as follows: The front disk face is defined as the disk face where the pressure is pushing the perforated plate against the stiffening wires. In this case, the perforated plate is supported by the wires, spanning between the two adjacent wires. This face is subjected both to gravity plus seismic loads, as well as operating differential pressure (DP).The back disk face is defined as the disk face where the pressure is trying to pull the perforated plate away from the wires. In this case the perforated plate is supported by discrete points at the rivet locations and the rod spacers. This plate bends in a 2-way action between the rivets. This back face is only subjected to gravity plus seismic pressure as the operating differential pressure (DP) only acts inward.The outer rims are subjected to both seismic load and operating differential pressure.

The outer rim is essentially the web of the edge channels and is continuously supported along the edges by the disk faces through the rivets.Since the depth of the disk is only 1/2", the outer rim stress is much less than the disk face stress and is therefore OK by comparison.

The inner gap plates simply consist of a thin, flat, circular ring. The gap plates are supported at discrete points by the inner rods. Because of the complex stress distribution due to the curvature and the discrete support points, the stresses in the inner gap are calculated using finite element analysis using ANSYS software.

Buckling is also evaluated.

The stresses for the front face are calculated by hand based on Reference

[17]. A unit width of perforated plate is considered, subjected to a uniformly distributed load. The plate acts as a continuous beam simply supported at each radial wire, and simply supported at the edges. Since the beam is continuous, the stresses in the perf plate are based on a fixed-fixed beam with a span equal to the maximum wire spacing. The figure below depicts this model.I I IF-

_ Automated Engineering CALCULATION SHEET Page: 71 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes No No Date: 08/25/06 6.7.1 End Disk Perforated Plate Check Front Disk Face Per Timoshenko (Reference

[17]), the stresses in the plates acting as tension members can be determined as follows: The maximum span between wires for the vertical sides was calculated previously in section 6.1 and found to be: Ls:= max(Slrad, S2rad)Ls = 3.20 in The pressure acting on the perforated plate on the end disk was calculated in section 6.7 as: q := qend.disk.0 q = 1.56 psi The ends can be considered fixed because of the continuity of the perforated plate, therefore, refer to Section 3, of Chapter 1, of Reference

[17].Eeff-tperf3 12.(1 -veff)Eeff /tperf )4-U := ( -V eff 2) -_q ' ." -s )D = 211.6 in-lbf U1 = 0.8506 UAutomated Engineering CALCULATION SHEET Page: 72 of 107 Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 Solving Eq. (15) for u u := 0.08 (initial guess)S81 27 U-= root U1 + 7 27 16.uT.tanh(u) 16.u 6.sinh(u)27 9 4.u 8 8.u 6 'u)3-(u -tanh(u))u 2tanh(u)(direct tensile, or membrane stress)Eeff-u 2 2 tperf 2 (b 3.e(1n s eff) s (bending stress)U = 0.09 V= 1.0 cai = 0.029 ksi q. S22* -=c2 = 5.70 ksi The membrane plus bending maximum principal stress is, cyfront =(a1+ Gr 2)cGfront = 5.73 ksi The allowable stress is defined in Section 3.0 as Sall.pI := 1.5.S cGfront IRface.dp

-Tatl.p a The deflection at midspan between stiffeners is, Sall.pl = 26.85 ksi I Rface.dp = 0.21 6 = 0.002 in (2h 241 u u u f+ -( I" 4 2 sinh(u) -tanh u))fl = 1.0 q-S4 q3.L 384. D U11M Automated Engineering CALCULATION SHEET page: 73 of 107< Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 Check End Disk Face for Back Pressure For the differential pressure case the internal wire stiffeners provide support to the perforated plate because the pressure acts inward. However the gravity plus seismic pressure due to acceleration can act either inward, or outward. The outward pressure case is like a back pressure trying to pull the perforated plate off of the strainer.in this case the only thing holding the plate on is the rivets at the edge channels, and the inner gap plates for the middle disk faces, or the collar for the end disk face.To analyze this condition, consider the plate as an annular plate with an equivalent area, simply supported at both the inner and outer edges. The analysis is based on Roark and Young (Reference

[16], Table 24, Case Number 2c.). This is the same case evaluated in Section 6.4.2 to determine how much load is tributary to the edge channels, or to the inner rods, therefore all of the C and L constants are already defined. Reference 16 also provides the formula for the moment in the plate as a function of the radius. A solve block is used to solve for the maximum moment because the location of this maximum moment is unknown. Note that the units must be removed prior to entering the solve block. The maximum seismic stress is calculated (SSE) and conservatively compared to standard allowables.

qend.disk.2 Eeff tperf qbp.obe .- Ebp -tbp .-psi psi in 3 D -Ebp'tbp Mrb:= 0 12(1 -veff)An equivalent outer radius "a" is determined based on a equivalent area Ll disk.L 2 diskOgp a:= -a = 15.80in b:= ODgap b= 7.87in I2 a b a:= -a= 15.80 b:= -b= 7.88 ro:= b in in The rotation and reaction at the inner edge are solved for based on the previously determined constants Ob=-qbp.obe-a 3C3"L17- C9'Lj1 Ib=-00 Cp Cb-:=.C 7 .b =-0.00 S D C1 -C9 -C3.C7 ( e C 1.L 1 7-C 7.L--, Qb := qbp.obea' a I.C9 -C 3.C 7) Qb = 0.18

_ Automated Engineering CALCULATION SHEET Page: 74 of 107 Services Corp Calc. No.: PCI-5464-SO 1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes No ED Date: 08/25/06 Initial guesses must be made for all variables within the solve block prior to entering the solve block.Initial guesses: a+ b 2 F7 := -'-(I -Veff2) ---L8 +veff+ veff){b]F9 := b e -In (r +/-+ veff b1 2 r b 4r I I -V e ff r l _( o) 2 G 1 7:= -- I -1 e --I + (I + veff).ln -.(r- ro)0 D 2 Mr(r, F 7 , F 8 , Fg,G 1 7) Ob---F7 + Mrb-F8 + Qb.r.F9 -qbp.obe.r

'G 1 7 r Solve Block Given 1 lv ff2)9 ( r )F7 = --(I -veff+ -b-F8 = IL1 + Veff + -veff L -F9 --Ine + 1 r b 4 r'-rveff .r ]_ r _r -)0 G 17 =1 --1+ ,1 + Veff,.In (o (r-ro Var:= Maximize(Mr, r, F 7 , F 8 , F9, G 1 7)T

/, Automated Engineering CALCULATION SHEET Page: 75 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Wafts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes No D Date: 08/25/06 Mbp:= Mr(Vari, Var 2 , Var 3 , Var 4 , Var 5).lbf in.lbf Mbp = 0.26 -in Disk face stresses: Gback:= 6. MbP .Kpp tperf cy back lRface'bp

-Saii.pi G back= 1.13 ksi IRface.bp

= 0.04 6.7.2 Middle Disk Perforated Plate The geometry and pressure on the middle disk faces is the same as for the end disk as is the geometry, therefore the stresses in the middle disk faces are bounded by those calculated above for the end disk faces.

U Automated Engineering CALCULATION SHEET Page: 76 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes No ' Date: 08/25/06 6.7.3 Inner Gap Perforated Plate The stresses in the inner gap are determined using finite element analysis using ANSYS to take advantage of the added strength associated with the curvature of the inner gap. The parameters used in the ANSYS model are shown below. Note these dont match the Watts Bar configuration however the stresses are adjusted later to account for the differences between the model and the actual configuration.

Width = 1in ODgap = 18.48in ODspacers

= 0.84in Thickness

= 0.0478in (18 ga.)i 048 Kpp = 2.12 Effective poisson's ratio = 0.3 Effective modulus of Elasticity

= 1.28X1 0^7 psi Case 1 -Seismic Pressure Case 3 -Differential Pressure Figure 6.7-1 ANSYS Model of Inner Gap Perforated Plate Page: 77 of 107 Caic. No.: PCI-5464-S01 Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E- No D-I Date: 08/25/06 The model includes the full 360 degrees of the gap plate. The cross section is just a thin flat plate, modeled as an equivalent plate to account for the perforations.

The model is supported at four discrete points along the circumference at the inner rod locations.

One way supports are used such that they only restrain the plate from displacing inward, but offer no resistance if the plate wants to pull away from the rods. Three cases of unit load pressure (1 psi) are applied. Case 1 is for all the pressure in the vertical direction.

Case 2 is similar, but with the pressure acting in the lateral direction.

Case 3 is for the differential pressure (operating pressure) with all pressure acting radially inward. A fourth combined case is run with the initial guesses for the actual pressures in each direction.

The stresses shown below are from the combined case using the actual pressures.

The pressures used in the ANSYS model and the actual calculated pressures are as follows: Load Case Case 1 -Vertical Case 2 -Horizontal Case 3 -Radial Used in ANSYS qy.ans:= 0.07.psi qz.ans := 0.15. psi qr.ans := 1.37.psi Actual Pressures qgap.2 = 0.02 psi qgap.2 = 0.02 psi qgap.0 = 1.52 psi The ANSYS results are scaled up by the worst case increase from any of the three load cases. Stress plots are included on the following pages. The scale factor (Kp) accounts for changes in pressure, the Kpp factor, and the thickness of the perf plate in relation to the parameters used in the actual analysis M qgap.2 qgap.2 qgap.0o Kpp 0.0478.in qy.ans qz.ans ' qr.ans ) 2.12 tperf Kp = 1.06 Note that the ANSYS model was run for a 18.5" OD Gap ring which is larger than the 15.75" gap ring for Watts Bar. The use of a larger diameter is conservative.

Automated Engineering CALCULATION SHEET Page: 78 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit I Prepared By: Curtis J. Warchol Caic. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes El No [I Date: 08/25/06 TIE,=1 HIMr (NoAvr)iOU .0571ts 3MU =17.t66 iP~i~yv Beach Im.,K.e i. platKe AN 55E2 +/-005 10 +/-1 55 17.266 371.744 726.222 1081 1435 1790 2144 2499 2953 32091 Figure 6.7-2 Inner Gap Plate Membrane Plus Bending UTl4:l SUB z15 7 TINE:I SIMt (3l0AVf UBt * .75 SEW = '1 0$AN DEC 2t 2005 10; : 45 17.256 371.744 726.222 1081 1435 1790 2144 2499 2853 L 06 FigurBeac 6.7i-3 Inne GapPlate Mebrn PusBndng(loe-p Figure 6.7-3 Inner Gap Plate Membrane Plus Bending (Close-Up)

/i~ Automated Engineering CALCULATION SHEET Page: 79 of 107 Services Corp Caic. No.: PCI-5464-SOI Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Caic. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes a No [I Date: 08/25/06 ELUM MUHMAN 3T lDE1 Z 1 Z 31D .15 1,0l2514 TXME-1 slur (10"', 277.022-sm 17.O1 415.173 455.225 491. 475 529.6527 567-778 605.929 644.081 682.232 S720. 505 P.int Beach ft.aine. 1- Ri. plate maly.i.Figure 6.7.4 Inner Gap Plate Membrane Stress I Figure 6.7-5 Inner Gap Plate Membrane Stress (Close-Up

1)

Automated Engineering CALCULATION SHEET Page: 80 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit I Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes [ No [] Date: 08/25/06 Figure 6.7-6 Inner Gap Plate Membrane Stress (Close-Up 2)Figure 6.7-7 Inner Gap Plate Displaced Shape

_ Automated Engineering CALCULATION SHEET Page: 81 of 107 SServices Corp ,Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes l No EI Date: 08/25/06 The ANSYS output is included as Attachment D. The maximum membrane principal stresses occur at the support locations.

These stress are already adjusted in ANSYS to account for the Kpp factor. The stresses from ANSYS are scaled down on the ratio of Kp.cygap.mem:

720psi-Kp Ggap.ben := 3200.psi.Kp cgap.mem = 0.76 ksi agap.ben = 3.39 ksi The allowable stresses are taken from Section 3.0 as Smem:= 1.0-S Sben := 1.5.S Smem = 17.90 ksi Sben = 26.85 ksi The Interaction Ratio is therefore:

(%mgap.mem cygap.ben IRgap :=max 5 , mem Sben )IRgap = 0.13

_ Automated Engineering CALCULATION SHEET Page: 82 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 In addition to bending stresses calculated on an elastic basis, buckling of the innergap ring is also examined.

A buckling evaluation is performed based on Sections 7.3 through 7.6 of Timoshenko's Theory of Elastic Stability (Reference

[32]).Since the gap disk will be supported at the tension rods and periodically between each tension rod by tabs off of the strainer disks, the buckling mode of the gap disk will reflect the higher modes of buckling for the circular ring discussed in Section 7.3 of Reference

[32]. Due to symmetry, the equations for the circular arch under uniform pressure discussed in Section 7.6. will have the same results as the circular ring from Section 7.3. This.can be seen by comparing equation 7-20 from Section 7.6, where a=n/2 , with equation 7-12 from Section 7.3.The critical pressure that will cause buckling is calculated using equation 7-20 of Reference

[32], since the modes of buckling of equation 7-12 have the same result in equation 7-20 by changing the value of 0 such that 2 n/0 is the mode represented in equation 7-12.Fig. 6.7-8 Inner Gap Buckling The parameters for the evaluation are as follows: a := 30.deg a = 0.52 hg := tperf hg = 0.0595 in ODgap R= .- R =7.87 in 2 maximum angle between supports (Reference

[6x])Perforated plate thickness Radius of gap ring U Automated Engineering CALCULATION SHEET Page: 83 of 107 jServices Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 Since the buckling of this arch depends on the inextensional deformation of the arch, the buckling mode resembles that of the second mode of buckling of a column, with an inflection point in the center. It is possible that a support, tab or tension rod, may occur at this inflection point. The radial span of the arch, 0 = 2 (x, is then the span between three supports.

Since higher modes of buckling have higher critical pressure, and the odd modes of buckling for a circular ring are rather complex, the critical pressure of the gap disk for the maximum support spacing will be determined.

Eeff'hg3 7E2 qcr= 12( --veff2).R" o Eq. 7-20, Reference

[321 A factor of safety consistent with AISC buckling allowables is applied to the gap disk pressure: 23 FSqcr := -12 The critical pressure resulting from the assumed mode, if the maximum support spacing was spread around the entire gap disk, is: qcr: -Eeff hg 3 "2 120( -veff2).R3 a 2 qcr = 15.17 psi The Interaction Ratio for the buckling of the gap disk is: IRgap.buck

-qgap.o.FSqcr IRgap.buck

= 0.19 qcr I Page: 84 of 107 Calc. No.: PCI-5464-SOI

+Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 6.8 Wire Stiffener Evaluation The radial wire stiffeners support the perforated plate for the differential pressure condition (operating pressure)The radials on each side support the adjacent face. The radials themselves are supported by the circumferential wire stiffeners in between the two radials. The length and support span of the radial stiffeners was previously calculated in Section 6.1 as: Ll wire = 5.91 in S 1 rad = 3.20 in L 2 wire 5.91 in S 2 rad = 3.20 in The bending moment in the wire is conservatively calculated as a pin-pin beam supported between circumferential wires.(qeda)_( L 2 wire (qend.core.o S2r Ncirc + 1 2-2]8 8 Mrad = 5.44 in-lbf Swire.rad

0.00054 in 3 7E 3 Swire.rad:

-dwire.rad 32 Mrad 0 wire.- -Swire.rad Salt.bar:=

0.75.Sya Gwire IRwire -Sall.bar Gwire = 9.99 ksi (per 1.5.1.4.3 of AISC (Reference

[91)Sall.bar -' 19.13 ksi IRwire = 0.52 Note the corner radials are OK by comparison as they have near a similar span, but they are doubled up so there are two wires side by side to carry the load.The circumferential stiffeners are only in bearing and can easily accommodate the loads and do not require a detailed evaluation.

_ Automated Engineering CALCULATION SHEET Page: 85 of 107 Services Corp Calc. No.: PCI-5464-S01 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes [ No E-] Date: 08/25/06 6.9 Core Tube End Cover Evaluation 6.9.1 End Cover Perforated Plate The stiffening pattern for the end cover on the core tube is shown on Reference

[6i]. The dimensions are given in Section 5.2. There is only inward pressure primarily due to DP. There is no outward pressure from seismic because the vertical seismic loads are less than deadweight thus there is no uplift on the end cover.The method used to calculate stresses is similar to that used for the end disk in Section 6.7.1 Per Timoshenko (Reference

[17]), the stresses in the plates acting as a tension member can be determined as follows: The span between stiffeners is v:= I .. Ncirc.end

+ I ODtube Ls.end --Rcirc.end if v = Ncirc.end

+ I V 2 V Rcirc.endv+

1 -Rcirc.end otherwise a :=V Ls~max= max(Ls.end)

Len (3.62)/ in Ls'endz =2.50 n Ls.max = 3.62 in The maximum pressure is q := qend.core.0 q = 1.56 psi The ends can be considered fixed because of the continuity of the perforated plate, therefore, refer to Section 3, of Chapter 1, of Reference

[17].Eeff ( tperf Ul _ [(l -veff2).q q.(Ls.max-)

U1 = 0.3165 3 Eeff 'tperf 12.(1 -veff2 D = 211.65 lbf.in I Page: 86 of 107 Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No 0 Date: 08/25/06 Solving Eq. (15) for u u := 0.1 (initial guess)u := root UI + 781 + 6.2 78 -96, u 16.u.tanh(u) 16.u 6.sinh(u)2 4u 8 8u6u U = 0.15 3.(u -tanh(u))u 2.tanh(u)= 1.00 (direct tensile, or membrane stress)Eeff'u 2 tperf 2 3.(1 -veff2) ".Ls.max 2 1 = 0.062 ksi (bending stress)q Ls.max 2 0 2 :: -"( tperf 0G2 = 7.29 ksi The membrane plus bending maximum principal stress is, oyfront.end

= (c.1 + G2)(membrane plus bending dearly controls.o'front.end

= 7.35 ksi o'front.end IRfront.end

=Sall.pl IRfront.end

= 0.27 (membrane plus bending dearly controls)24 2 iu u fl: 4' ( +,sinh(u) tanh(u))fl = 1.00 q ' Ls.max 4 6= .- "f 56 = 0.003 in 384.D (deflection at midspan between stiffeners)

Automated Engineering CALCULATION SHEET Page: 87 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 6.9.2 End Cover Stiffener Evaluation In this section, the end cover stiffeners are evaluated.

The radial spokes are conservatively evaluated as independent beams spanning the ID of the core tube.Lspoke:= Dcap Lspoke = 13.50 in The load on the spoke is a fu nction of the tributary width of each spoke. This is maximum at the edges of the core tube and reduces down to zero at the center of the core tube.7t Dcap qspoke:= qend.core.0" --Nspoke lbf qspoke = 8.25 -in The spoke is considered a pinned-pinned beam spanning the diameter of the end cover sleeve. The moment is maximum at center span. This determinate beam is shown below.L spoke q spoke V I f I FF I F Figure 6.9-2 -Beam Diagram for End Cover Spokes The reaction at the supports is qspoke'Lspoke Vspoke := 4 Vspoke = 27.83 lbf

_ i Automated Engineering CALCULATION SHEET Page: 88 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit I Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No 0 Date: 08/25/06 The maximum moment for such a load case occurs at center span (1/2 Lspoke), therefore, the moment at the center of the beam is: Mspoke := Vspoke" 6 The properties of the spoke are: Mspoke = 62.62 1bf in Aspoke := Wspoke~tend 1 2 Sspoke :- Wspoke~tend The stress in the radial spoke is Mspoke aspoke.- Sspoke IRspoke .- sp Sall.pl The shear stress in the spoke is small Vspoke Tspoke:- Aspoke Aspoke = 0.09 in 2 Sspoke = 0.0059 in 3 (7spoke = 10.69 ksi IRspoke = 0.40 Tspoke = 0.30 ksi Automated Engineering CALCULATION SHEET Page: 89 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sumn Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 6.9.3 End Cover Sleeve Evaluation The "spider" end cover stiffener is welded to the end cover sleeve with a 1/8" two-sided all-around stitch weld. When analyzing the spokes of the end cover stiffener in Section 6.9.2, the spokes were conservatively considered pinned-pinned.

However, for evaluation of the welds and sleeve, it is more appropriate to analyze the spoke as a fixed-fixed beam spanning the ID of the core tube end cover sleeve.The moment is then maximum at the connection to the sleeve. Based on this conservative assumption, an edge moment at the end of the end cover sleeve is produced by the front pressure case of the end cover perforated plate (seismic plus differential pressure, Section 6.9.1). Before analyzing the end cover sleeve, this moment must first be determined.

The indeterminate beam is shown below. The moment is solved for by superposition.

First the rotation for the pinned-pinned beam under the same loading is determined.

Then this is superimposed with a pinned-pinned beam with edge moments that produces the same rotation to determine the edge moment. The rotation at the end of the pinned-pinned beam is determined by summing the area under the curvature diagram. The equation for the moment of the beam is solved for on the next page.L spoke qspoke_2_!Figure 6.9-3 -Beam Diagram for End Cover Spokes (fixed-fixed)

> I Automated Engineering CALCULATION SHEET Page: 90 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes W No D1 Date: 08/25/06 The equation for the moment at any point "a" for the pinned-pinned beam is written as follows.The reaction at the support is Vspke qspokeLspoke Vspoke = 28 Ibf The magnitude of the distributed load at any point a distance 'x" from the support is (0.5.L-spoke

-Wx = qspoke' 0.5.Lspoke Therefore, the equation for the moment at any point "a" is Ma = qspokeiLspoke 1 a o-0.5 Lspoke -x.(a -x) dx 4 ý 0..5.Lspoke 0 This can be solved symbolically as 1 1 .qpk~ -3 Ma =

+ " qspok (a spok" The deflection at the end is equal to the area under the moment diagram, or 1 0.5. Lspoke OA= Ma da where, E.Ispoke J 0 1 3 Ispoke :=-j-.Wspoke~tend Ispoke = 0.00110 in 4 0.5. Lspoke OA:{0 1 1 2 2.a- 3.Lspoke-"qspokeLspoke'a

+ ;qspokea Lspoke da Esailspoke OA = 0.60 deg Per Reference

[35], the rotation for a pinned-pinned beam subjected to equal and opposite end moments is= Mspdr Lspoke 2.E.Ispoke Page: 91 of 107 Calc. No.: PCI-5464-SO1 Revision:

2 Client: Performance Contracting Inc.Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes W No D Date: 08/25/06 Setting 0 A equal to Om, Mspdr can be determined 2.Esa Ispoke Mspdr:= .OA Mspdr = 46.97 Ibf-in Lspoke Therefore, the edge moment per unit length on the end cover sleeve becomes M Mspdr" Nspoke M= 8.70 in M° : (Dcap + 2.tcap) in In order to analyze the effect on the sleeve due to this edge moment, consider Case 3 of Table 29 (Reference

[16]) for an edge moment along the entire circumference of a tube.Esa'tcap 3 Dcover: 12(1 -v2) Dcover= 4346 lbf-in 3(1 -1 Xcover:= ?Xcoverz=

1.42-Dcap + 2 .tcap2)p 2 in 2 C 1 1 := sinh(Xcover-wcap)

-sin (Xcover.wcap) 2 Cl 1 = 85.81 C 1 4:= sinh(Xcover.wcap) 2 + sin (Xcover.wcap) 2 C1 4 = 85.91 The stress in the end cover sleeve due to the edge moment is Mo C 1 4* 2~ Cl Esa 2.Dcover.Xcover 2 C 1 1 acvr.slv -0 cvr.slv = 2.05 ksi 0.5.Dcap Therefore, the Interaction Ratio for the end cover sleeve is-slv'I Rc(0.13)IRcvrslv :(0.6'Sya (IRcvrsl = .09 U Automated Engineering CALCULATION SHEET Page: 92 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes EE No 0 Date: 08/25/06 6.10 Weld Evaluations 6.10.1 End Cover Stiffener Weld Evaluation (Horizontal Strainer Module Only)The "spider" configuration of the end cover stiffener is welded to the end cover sleeve with a 1/8" two-side all around weld (1" at 4" centers), see Figure 6.13-1 below. The weld pair acts as a force couple to resist the moment at this location caused by the pressure loads acting on the spider configuration (front pressure case of the end cover perforated plate controls, see Section 6.11.1). A normal force also acts on the welds due to the front pressure case.Nspoke = 8 Dcap= 14in tend = 0.38 in Vspdr.1 I DP.- .Dcap 2 4 Vspdr.1 :=7-Dcap lbf Vspdr.1 5.1 i in Mo Vspdr.2 ' tend -0.125 -in lbf Vspdr.2 = 35-in Vspdr.2 *V spdr.2 -- -Sleeve I Figure 6.10-1 -End Cover Stiffener Welds c~w.spdr:=

Vspdrl 2 1 + Vspdr.2 .(4 lbf Gw.spdr = 141-in The ultimate tensile strength of the weld material employed (ER308 electrode) is: Fu := 75.ksi (Reference

[251)

U Automated Engineering CALCULATION SHEET Page: 93 of 107 Services Corp Caic. No.: PCI-5464-S01 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes El No -Date: 08/25/06 Weld allowables are per the AISC Manual, Reference

[9]0.3"Fu.0.707"1 Fweld.1 :0.3.Fu.0.707.1.6 (0.4.Sya Fweld.2:=

0 ;ya Fweldh := min (Fweld.l h, Fweld.2h)Fweld.spdr

= Fweld~tw.spdr'(Shear on effective throat)(Base metal shear)(15.9 Fweld'l = 25.5 ksi (10"2)ks Fweld.2 = k13.3 (10-21 Fweld = I ) ksi F s 13.3)Fweld.spdr

= 16756) Ib-OYw.spdr IRw .spdr :=Fweld.spdr IRw.spdr =6.10.2 Radial Stiffener to Core Tube Weld Evaluation In this section, the weld between the end core stiffener collar and the core tube is evaluated.

The weld pattern includes a 1.5" weld between the core tube and the stiffener collar on either side of a radial stiffener location such that there is a 1.5" space between two adjacent welds. This results in a total of 4 weld groups, at each end of the strainer module.The weld properties are as follows: tw.ct = 0.06 in ww.ct= 1.50 in Nd 7Lct T _Node -Wstfnr Ww.ct Aw.ct:= 2.Ww.ct Aw.ct 3.00 in Lw.ct= 5.25 in Lw~ct:=z 2 ww~ct+ wstfnr U Automated Engineering CALCULATION SHEET Page: 94 of 107 Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes EN No D / Date: 08/25/06 3 3 Lw.ct -Wstfnr Zw .ct.z := 6 w t Ww.ct 3 (Ww.ct + Wstfnr)2.Ww.ct 6 2 Zw.ct.z = 4.23 in 2 JW.Ct= 11.11 in 3 The maximum axial forces, shear forces, and moments found at the stiffener-to-core tube weld locations for the OBE and SSE earthquake are extracted from the GTSTRUDL analysis (Attachment B). Load Combination

0 is enveloped by Load Combination

1 and is not specifically evaluated.

The reactions from the end cover sleeve are also added to the shear in the z-direction.

Pwctx: 0 lI f OBE (0.). SSE Vw.ct.y:=

C19j.bf Mwctx:C 0 lbf in Mw.ct.y:=

0 ,lbfin Mw.ct.z:,=

0lbf-in Members RIGID1 -RIGID32 End Joints Vw.ct.z:= .lbf + Vspdr.1 Dcap 42 4[2 Vw.ct.y 1 IVw.ct.z Mw.ct.x Lw.ct +2 Pw.ct.x Mw.ct.z)2 (47.71 )bf fw.ct:= [,y) + Aw.ct +w.ct 2 ) + Aw.ct Zw.ctzj fw'ct= 71.3 in OBE SSE Fweld.ct:=

Fweld~min(tw.ct, ttube)E 610 lbf Fweldct = 792 in IRweld'ct

= I0.09 (0.092 fw.ct IRweld.ct

-Fweld.ct 6.10.3 End Cover Mounting Tab Welds The strainer end core cover is secured to the end of the last strainer module via rectangular tabs that are welded to the side of the end cover. Holes are drilled into these tabs such that they fit over the inner tension rods, after which nuts are tightened down capturing the tabs and therefore securing the end cover to the strainer module. These tabs will only be subjected to a normal force at their ends when there is a force trying to pull the perforated plate off the core tube (back pressure).

Since the end cover is not subjected to back pressure (dead weight exceeds seismic and acts down) the mounting tabs and their welds do not see any significant loads and are acceptable.

Page: 95 of 107 Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Caic. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes El No D Date: 08/25/06 6.11 Evaluation of Local Stresses in Core Tube at Connection to Radial Stiffener The local stresses that develop on the core tube at the weld of the radial stiffener are very small due to the presence of the collar. These welds primarily transfer shear to the core tube. Shear loads at the welds will produce very minor local stresses.

As can be seen from the weld stress calculation, the weld stresses are very low.6.12 Rivet Evaluations In this section, the various rivets are evaluated to ensure they are capable of transferring the required loads.The rivets are broken into three subsets as follows: Disk Face to Edge Channel Rivets Inner Gap Hoop Rivets End Cover Rivets The rivets capacities are based on testing from Reference

[18]. The capacity of the rivets is taken as the average value from six tests (for both shear and tension).

During testing, the rivets were subjected to double shear.Some rivets being evaluated in this section are in single shear, therefore, the double shear ultimate capacities are halved. The ultimate capacities of the rivets are as follows: n1 := 6 Test Test Frv.sh.ult

= I-'2"1533.6 1289.3 1409.5 1526.6 1495.4 11300.3).Ibf Al -Al -Al -A2 -A2 -'A2 -A B C A B C 892 970 897.2 879 798.4 931.Ibf C1 C1 C1 C2 C2 IC2-A-B-C-A-B-C n1 y Frv.sh.ulti i=1 Frv.sh.ult.avg:=

n Frv.sh.ult.avg

= 712.89 lbf n1 Frv.ten.ulti n1 Frv.ten.ult.avg

Frv.ten.ult.avg

= 894.60 lbf U Automated Engineering CALCULATION SHEET Page: 96 of 107 Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes a No El Date: 08/25/06 Since the ultimate capacities of the rivets are found experimentally via a small sample group (n = 6), the ASCE Standard (Ref. [22]) is used to derive a factor of safety to qualify the rivets. The ASCE Standard is supplemented by the AISI Specification (Reference

[51) as needed for the Factor of Safety equation and for variable values not provided in ASCE. The following variables and their corresponding values can be found in section 6.2 of ASCE (Ref. [221) or in subsection F1 of AISI (Ref. [5]) for screw connections when not specified by the ASCE Standard (Ref. 122]).n1n nl-1 n (Frv'sh'ult

-Frv.sh.ult.avg) 2 iH n1 I Vp1 Frv.sh.ult.avg Frv.ten.ult.avg Vpl = 0.078 Vp1 := if(Vpl > 0.065, Vp 1 , 0.065)DOFI:= nl -1 Pml : 1.0 Fmi 1.0 Mmli 1.10 Vp1 = 0.078 VQI := 0.21 VM1 0.10 VF1 0.05 n1 -1 Cp1 n1 -3 Cp1 = 1.67 (Eq. 6.2-3, Ref. [22])3 ol := 4 v 2 2 2 2 4 brivet :1.5.(Mmi .Fmi .Pml)-e- +V F 1 + IV1 +V12 4~rivet = 0.59 (Eq. 6.2-2, Ref. [22])1.6 4 rivet FSrivet := + .(CT + 1)- rivet FSrivet = L2.72)(Eq. F1.2-2, Ref. [5])

UAutomated Engineering CALCULATION SHEET Page: 97 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. I Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06 6.12.1 Disk Face Rivets The shear and tension on the disk face rivets is calculated based on calculations performed in earlier sections of this calculation.

The shear on the rivets is taken as the shear resulting from the shear transfer required for the edge channels and the perforated plate to act as a composite section, combined with the shear associated with the lateral loads on the disk rims and gaps.The shearflow due to combined section is based on the following standard beam shear equation, or V.Q q--whe re V = the maximum shear carried by the combined perf plate / edge channel section Q = the first moment of inertia of the cross sectional area supported by the rivets I = the combined moment of inertia of the perf plate / radial stiffener section The maximum shear force for the edge channels is taken from the GTSTRUDL analysis (Attachment B).(4.9) OBE or DW+DEB Vrv .SSE I3.0) b SSE Member/Node (GROUP "CHANNELS')

The combined moment of inertia was calculated in Section 6.4.2 for the edge channel properties.

Irv := Ich.z'in4 Irv= 0.0107 in 4 Q is calculated below (the maximum Q values are used for each the end and middle disks)Qrv: beff tperf{dchan + tperf 2 Qrv = 0.0133 in 3 Therefore, the shear per rivet, factoring in the rivet spacing, is (VrvQrv frv.shl :ý -i .max (SiradS~rad;)

frv.shl 12.0)lbf Automated Engineering CALCULATION SHEET Page: 98 of 107 Services Corp Caic. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes El No LI Date: 08/25/06 This shear needs to be combined with the direct shear from lateral loads acting on the edge channels.frv.sh2 := qchan.O.dchan'max(Sl rad, S2rad)frv.sh2 = 2.43 lbf The total shear acting along the axis of each radial stiffener is2 frv.face := fsh + frv.sh2 Find Tension for Disk Face Rivets frv.face =19.8) lbf (12.3)The tension in the disk face rivets is based on the back face perforated plate evaluation in Section 6.7.1 qend.disk.2 Ll disk.L 2 disk -.ODgap 2 -Qb' .- --r'ODgap 4 in Trv.bp :=2-L 1disk + 2-L 2 disk-max (S1 rad, S2rad)Trv.bp = 0.33 lbf These tension forces are very small and can be neglected.

Therefore only rivet shear needs to be considered.

Based on this, the Interaction Ratio for the disk face rivets is: frv.face FSrivet Frv.sh.ult.avg 0.08 IRrv'face

= (.0.04 Page: 99 of 107 Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No 0 Date: 08/25/06 6.12.2 Inner Gap Hoop Rivets These are the rivets used to hold the inner gap together in a hoop. The finite element analysis assumes the hoop is continuous.

The shearload on the rivets can be determined from the finite element analysis (Attachment D). A hoop tension force can conservatively be estimated from the maximum membrane stress in the hoop. Assuming the membrane stress in all in the hoop direction is constant through the width of the hoop, the maximum tension (or compression) force would be, Wgap'~tperf Thoop:= Ggap.mem " Kpp Thoop frv.gap.hoop

-thoop Nrivet.hoop Therefore, the Interaction Ratio is frv.gap.hoop FSrivet IRrv.gap :=Fry. sh.ulIt. avg Thoop = 17.97 lbf frv.gap.hoop

= 9 lbf (0.03 IRrvgap = 0..03)J 6.12.3 End Cover Rivets These are the rivets that secure the perforated plate on the end cover to the end cover stiffener.

These rivets are only subjected to tensile loads during a seismic event (shear is negligible).

Note the end cover stiffener supports the load during operation under differential pressure.qend.core.2

= 0.011 psi 71 qend.core.2 " '" lDtube2 frv.end: :=-Nrivet.end frv.end"FSrivet IRrv.end :=Frv.ten.ult.avg frv.end = 0.09 lbf 0.0003 IRrv.end = .0.0002 Page: 100 of 107 Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes No D Date: 08/25/06 6.13 Connecting Bolt Evaluation The loads on the bolts that connect the modules are taken from the hex coupling internal forces. The maximum tension, shear and bending on any hex couple is Phex:= C5 bf/(383 ]2+ F(452 -1.2 Vhex:= L478) +ILbf 590) lbf 625 1]2 +(552. 2 Mhex:= "1 818 ) -inlbf + L698 inlbf Phex = C5) lbf Vhex = 592 Ibf 8(345 Mhex= (1075 in-lbf DW+OBE / DW+DEB+P DW+SSE DW+OBE / DW+DEB+P DW+SSE DW+OBE / DW+DEB+P DW+SSE The moment on the hex couplings results in additional tension on the bolts due to prying action. The maximum bolt tension is therefore:

.2-Mhex Tbolt:= Phex + --ODhex C1877>Tbolt = 1877) lbf (2446 Vbolt = 592 Ibf (759)Vbolt := Vhex The bolts are 1/2" A-193 Grade B8, Class II bolts. The allowable stresses are based on Reference

[22]1/2" diameter bolts are used to connect the strainers to the support tracks. The bolts are qualified in single shear (threads excluded) according to section 5.3.4 of the ASCE Standard (Reference

[221). Factors of Safety are found in Table D of Reference

[22] for both the tensile and shear cases of bolted connections.

Qten := 3 Qsh := 3 In order to account for the high temperatures that these bolts are subjected to, a factor is calculated based on the ratio of the ultimate strength of Type 304 Stainless Steel at -20 to 1000 F to Type 304 Stainless Steel at 1900 F.Su.304 := 75-ksi SUO Sem 5 u. 304 (Ultimate Strength of Type 304 Stainless Steel at -20 to 1000 F, Reference

[3])Otemp = 0.98 IL Automated M Engineering CALCULATION SHEET Services Corp Page: 101 of 107 Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No 0-I Date: 08/25/06 Per Table 6 of ASCE, the allowable nominal tensile and shear stress for stainless steel bolts with threads included in the shear plane are: 93.7.ksi.3temp 3.Ftbolt ten Ftbolt 30.57 ksi 1.6.93.7.ksi.1Ptemp (48.91 k f ten )( 56.2.ksi .temp Qsh Fb lt: 1.6.5 6.2.ksi.i 3 temp Fvbl 29.33)ks\ sh )The nominal bolt area is: b .ODbolt Abolt: .-Abolt = 0.20 in 2 Tbolt c ybo lt .-Abolt Vbolt t bolt :=Abolt (9.56 >cbolt = 9.6 ksi\b ( 12.46)The combined shear and tension loads on the bolt are evaluated in accordance with Section 5.3.4 of the ASCE Standard (Reference

[22]).Ft:= 1.25.Ft.bolt

-2.4.Tbolt Ft.bolth := mi n(Ft.bolt h, Ft%)Therefore the bolt Interaction Ratio is: (cybolth bolth lRbolth, := max I Ft.bolth Fv.bolth)(30.97>1 Ft = (30.97 I ksi (Equation 5.3.4-3, Reference

[22])k~51.85)(tbot 30.57 ) ks Ft'bolt- 48.91 ksi (0.31>IRbolt = 0.(~0.25, U11 Automated Engineering CALCULATION SHEET Page: 102 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Caic. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No Dl Date: 08/25/06 Required Preload The bolt/stud must be preloaded to ensure the joint doesn't separate during a seismic event. Using a methodology similar to that used for the spacer separation check in Section 6.4.8. Preload relaxation is not considered in this case because this joint is less likely to experience preload relaxation in comparison to the strainer tension rods.IPhex Vhex v -t I Li) % Seal Strip Figure 6.13-1 Hex Couple Connection To determine the required torque to prevent joint separation, examine the free body diagram of the hex couple above. The stud tension (T) initially is equal to the preload, which is also equal to the prying force (R). As the connection is loaded, the tension force from the strainer (F) effectively reduces the reaction force (R) by almost the exact magnitude (there will be slight differences due to the various stiffnesses of the bolts and connecting members).

The stud tension (T) essentially remains equal to the initial preload until the point where the joint separates.

In order to prevent joint separation, the preload must be greater than the applied force (F), but in addition, the preload must be sufficient to resist the moment resulting from the shear force (V). By summing the moments about the corner prying point of the hex couple, the stud tension (T), or the preload, times the lever arm, must exceed the moment in the hex couple due to the shear load (V). Therefore, the required preload is calculated based on the following formula.Knf = 0.30 (from Section 6.4.8)( Mhex max Phex2, 1.I56.in ODbolt'Knf 2)0.85-~0.80 Treq:=where: (0.85 for under torque tolerance)

(0.80 for torque to preload conversion uncertainty)

Treq = 34.2 ftlbf Use 40 ft-lbs plus or minus 15%(Note that a higher torque is permissible as long as the bolt is not structurally damaged during installation).

I Page: 103 of 107 Calc. No.: PCI-5464-S01

+Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No 0-- Date: 08/25/06 7.0 RESULTS AND CONCLUSIONS The results of this calculation indicate that the strainers meet the acceptance criteria for all applicable loadings.A summary of the maximum stress Interaction Ratios (calculated stress divided by allowable stress) is provided below. For the 3 column arrays, the first number shown is for Load Comb. #1 (DW+DEB+P), the second number is for Load Comb. #2 (DW+OBE), and the 3rd number is for Load Comb #6 (DW+SSE).Strainer Comoonent Ref. Section Welded Radial Stiffener (Including Collar)Tension Rods Edge Channels Cross Bracing Hex Coupling 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 Interaction Ratio T IRstfnr = (0.24 0.70 0.85)IRrod T= (0.46 0.46 0.42)T IRchan =(0.51 0.73 0.78)T IRcable = (0.00 0.30 0.41 T IRhex =(0.19 0.28 0.30)T IRtube (0.18 0.11 0.14)T IRbent (0.06 0.19 0.28)T I Rspcr =(0.80 0.86 0.82)I Core Tube Bent up Portions of Radial Stiffeners Spacer Spacer Separation Perforated Plate (DP Case)Perforated Plate (Seismic Case)6.7.1 6.7.1 IRspcr.s = 0.85 IRface.dp

= 0.21 IRface.bp

= 0.04 Page: 104 of 107 Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc.Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes [N] No [- Date: 08/25/06 RESULTS AND CONCLUSIONS (Cont.)Strainer Component Perforated Plate (Inner Gap)Inner Gap Buckling Wire Stiffener Perforated Plate (Core Tube End Cover DP Case)Radial Stiffening Spokes of the End Cover Stiffener Core Tube End Cover Sleeve Ref. Section 6.7.3 6.7.3 6.8 6.9.1 6.9.2 6.9.3 Interaction Ratio IRgap = 0.13 IRgap.buck

= 0.19 IRwire = 0.52 IRfront.end

= 0.27 IRspoke = 0.40 IRcvr'slv

(.0.13°0.09 IRw'spdr (1o.081)(10.081)IR weld 'ct = (0.08 (0.08)IRrv.face

= k0.04)](0.03/IRrv.gap = 0.03 IRrv.end ( 0.00)(0.31 IRbolt = 0.3 )(0.25 Weld of End Cover Stiffener to End Cover Sleeve 6.10.1 Weld of Radial Stiffener to Core Tube 6.10.2 Edge Channel Rivets 6.12.1 Inner Gap Hoop Rivets 6.12.2 End Cover Rivets 6.12.3 Connecting Bolts 6.13 Notes: 1. Envelope of Load Combination 1 (DW+DEB+P) and 2 (DW+OBE)2. Load Combination 6 (DW+SSE)Note 1 Note 2 Note 1 Note 2 Note 1 Note 2 Note 1 Note 2 Note 1 Note 2 Note 1 Note 2 Automated Engineering CALCULATION SHEET Page: 105 of 107 Services Corp Calc. No.: PCI-5464-SO 1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes E No D Date: 08/25/06

8.0 REFERENCES

[1] TVA Design Specification SQN/WBN-DS-2005-063-001, "Advance Design Containment Building Sump Strainers", for Sequoyah Nuclear Plant Unit 1 & 2 and Watts Bar Nuclear Plant Unit 1, Revision 00.[2] TVA Letter from H.R. Rogers to Framatome (J.P. Sheldon),

Subject:

Advanced Design Reactor Building Sump Strainers

-Revised Seismic Response Spectra -N2N-066, Letter No. 30M532, dated February 27, 2006.[3] ASME B&PV Code,Section III, Division 1, Subsections NB, NC, and Appendices, 1989 Edition.[4] ASME B&PV Code,Section III, Division 1, Appendices, Article A-8000, "Stresses in Perforated Flat Plates," 1989 Edition, No Addenda.[5] AISI Specification for the Design of Cold-Formed Steel Structural Members, 1996 Edition.[6] Performance Contracting, Inc.(PCI), Sure-Flow Suction Strainer Drawings.6a. PCI Drawing No. SFS-WB1-PA-71 00, "Sureflow Strainer Module Assembly -6 Disk", Revision 9.6b. PCI Drawing No. SFS-WB1-PA-71 01, "Sureflow Strainer Module Assembly -7 Disk", Revision 9.6c. PCI Drawing No. SFS-WB1-GA-00, "Sure-Flow Strainers General Arrangement", Revision 7.6d. PCI Drawing No. SFS-WB1-GA-03, "Sure-Flow Strainers General Arrangement Sections", Revision 9.6e. PCI Drawing No. SFS-WB1-GA-04, "Sure-Flow Strainers General Arrangement Sections", Revision 10.6f. PCI Drawing No. SFS-WB1-GA-08, "Sure-Flow Strainers Upper Seal Strip Layout", Revision 9.6g. PCI Drawing No. SFS-WB1-GA-01, "Sure-Flow Strainers General Notes", Revision 12.6h. PCI Drawing No. SFS-WB1-PA-7103, "Sure-Flow Strainers Sections and Details", Revision 6.6i. PCI Drawing No. SFS-WB1-PA-7104, "Sure-Flow Strainers Sleeves/Covers", Revision 7.6j. PCI Drawing No. SFS-WB1-PA-7102, "Sure-Flow Strainers Master Core Tube Layouts", Revision 4.

1 Automated Engineering CALCULATION SHEET Page: 106 of 107 Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit I Prepared By: Curtis J. Warchol Cale. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes WE No D Date: 08/25/06[7] "Formulas for Natural Frequency and Mode Shape," by Robert D. Blevins,1979,Van Nostrand Reinhold.[8] Mechanical Engineering Design by Joseph Edward Shigley and Larry D. Mitchell, McGraw Hill, 1983.[9] AISC Manual of Steel Construction, 7th Edition.[10] AES Verification and Maintenance File for GTSTRUDL Version 25.[11] ANSYS Verification File, Version 5.7.1, dated 9/28/2001, AESMN File No. AES.1000.0562.

[12] "Engineering Fluid Mechanics" by John A. Roberson and Clayton T. Crowe, 2nd Edition, Rudolf Steiner Press, 1969, Library of Congress Catalog Number 79-87855.[13] "Introduction to Structural Dynamics" by John M. Biggs, McGraw Hill, Copyright 1964.[14] AES Calculation PCI-5464-S02, "Evaluation of Advanced Design Containment Building Sump Strainers Plenum Assembly -Watts Bar Unit 1", Revision 2.[15] EPRI Document NP-5067, "Good Bolting Practices

-A Reference Manual for Nuclear Power Plant Maintenance Personnel".

[16] "Roark's Formulas for Stress & Strain" by Warren C. Young, 6th Edition, McGraw-Hill 1989.[17] "Theory of Plates and Shells" by Stephen P. Timoshenko and S. Woinowsky-Krieger, 2nd Edition, McGraw-Hill, 1959.[18] PCI Intra -company Correspondence from Greg Hunter, Dated February 20, 2006, Subject, "Testing of 3/16" Blind Rivets and 3/16" Closed End Rivets" (with test reports attached). (Attachment E)[19] ASME Publication, "Pressure Vessel and Piping: Design and Analysis," Volume 2, 1972, Components and Structural Dynamics, Paper Title " Design of Perforated Plate," by O'Donnell

& Langer Reprinted from Journal of Engineering for Industry, 1962.[20] "Marks' Standard Handbook for Mechanical Engineers", by Avallone, and Baumeister, 9th Edition, McGraw Hill.[21] "American National Standard ANSI/AISC N690-1994, "Specification forthe Design, Fabrication, and Erection of Steel Safety-Related Structures for Nuclear Facilities", including Supplement 1 dated April 15, 2002.[22] ASCE Standard SEI/ASCE 8-02, "Specification forthe Design of Cold-Formed Stainless Steel Structural Members".

Automated Engineering CALCULATION SHEET Page: 107 of 107' Services Corp Calc. No.: PCI-5464-SO1 Client: Performance Contracting Inc. Revision:

2 Station: Watts Bar Unit 1 Prepared By: Curtis J. Warchol Calc. Title: Structural Evaluation of Advanced Design Containment Building Sump Strainers Reviewed By: Kishore D. Patel Safety Related Yes EE No D Date: 08/25/06[23] PCI Calculation TDI-6010-04, "Debris Weights on Modules Calculation", Revision 4.[24] AWS D1.1/D1 .1 M:2002, "Structural Welding Code -Steel".[25] ANSI/AWS D1.6:1999, "Structural Welding Code -Stainless Steel".[26] "Guide to Design Criteria for Bolted and Riveted Joints", 2nd Edition, published by the American Institute of Steel Construction (AISC).[27] Cable Vendor Data, PCI Transmittal 6003-04 (Attachment G)[28] Stainless Steel Sheet Thickness Table from Hendrick book. (Attachment F)[29] TVA Letter from H.R. Rogers to Framatome (J.P. Sheldon),

Subject:

Advanced Design Reactor Building Sump Strainers

-Component Design and Analysis Clarifications-N2N-066, Letter No. 30M354, dated March 30, 2006.[30] TVA Letter from H.R. Rogers to Framatome (J.P. Sheldon),

Subject:

Advanced Design Reactor Building Sump Strainers

-Component Design and Analysis Clarifications-N2N-066, Letter No. 30M536, dated May 1, 2006.[31] ASTM Specification A-276-02a, "Standard Specification for Stainless Steel Bars and Shapes"[32] "Theory of Elastic Stability," by Stephen P. Timoshenko and James M. Gere, 2nd Edition, McGraw-Hill, 1961.[33] ASME B&PV Code,Section III, Division 1, Subsections NB, NC, and Appendices, 1998 Edition.[34] ASTM Specification A-193/193M-99, "Standard Specification for Alloy-Steel and Stainless Steel Bolting Materials for High Temperature Service"[35] Design of Welded Structures", by Omar Blodgett, The James F. Lincoln Arc Welding Foundation, 12th Printing 1982, Library of Congress No. 66-23123.

v t e Letter Sequence Supplement
TAC:MC4730, (Open)
Initiation Request, Request, Request, Request, Request, Request Acceptance Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement Administration Withholding Request Acceptance Questions 3 June 2005 10 February 2006 3 December 2008 29 September 2009 23 December 2009 7 January 2010 17 June 2010 15 April 2011 28 June 2011 Answers 11 April 2006 3 March 2009 12 May 2011 Results Approval... Other: ML062910513, ML062910522, ML063060251, ML073380152, ML090720869, ML101590556, ML11230B250, ML15191A183
MONTHYEAR2008-03-31 [Table View]

ML081090502

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2.0 METHODOLOGY

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8.0 REFERENCES

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