ML18102B020

From kanterella
Jump to navigation Jump to search
Rev 0 to Evaluation of Structures for Increased Temps Due to Updated Main Steam Line Break.
ML18102B020
Person / Time
Site: Salem  PSEG icon.png
Issue date: 02/28/1996
From:
Public Service Enterprise Group
To:
Shared Package
ML18102B015 List:
References
S-C-ZZ-SEE-1048, S-C-ZZ-SEE-1048-R, S-C-ZZ-SEE-1048-R00, NUDOCS 9705050064
Download: ML18102B020 (21)
v • d • e


Text

ATTACHMENT 3 PSE&G ENGINEERING EVALUATION S-C-ZZ-SEE-1048 EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK

S-C-ZZ-SEE-1048 Date: Februa 1996

  • TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK 1.0 PURPOSE.................................................................................................................... 2 2.0 SCOPE ......................................................................................................................... 2 3.0 DISCUSSION............................................................................................................... 2

3.1 BACKGROUND

............................................................................................... 2

3.2 DESCRIPTION

OF STRUCTURES................................................................ 3 3.3 METHOD OF REVIEW.................................................................................... 3 3.4 REVIEW RESULTS .....................................;................................................... 4 3.4.1 Containment Concrete Structure.....................................-..................... 4 3.4.2 Other Structures ................................................................................... 6 3.4.2.1 Containment Spray Piping Support Steel ............................................ 6 3.4.2.2Reactor Coolant Pump Access Platfonn.............................................. 7 3.5 PRESENT STATUS ......................................................................................... 7 3.6 FUTURE PLANS .............................................................................................. 8

4.0 CONCLUSION

S .. ....... ........ ......... ......................... ........................... .. ........... ........ ....... 8

5.0 REFERENCES

............................................................................................................ 8 6.0 IMPACT ON VENDOR TECHNICAL DOCUMENTS ................................................ 11 7.0 ATTACHMENTS .......................................................................................................... 11 7.1 LOAD COMBINATIONS ...................................................................................... 12 7.2 INVENTORY OF STEEL INTERNAL STRUCTURES ....................................... 14 8.0 SIGNATURES ............................................................................................................. 20 1 of20

S-C-ZZ-SEE-1048 Date: Februa 1995 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM UN EAK ATS ITEM:

1.0 PURPOSE This Engineering Evaluation report is prepared to provide a brief description of various engineering activities used in the evaluation of Salem Nuclear Generating Station ( Units 1 and 2) structures for increased temperatures due to updated Main Steam Line Break (MSLB). The evaluation was performed by comparing the increased temperatures due to updated MSLB with the LOCA event temperatures used for the original designs.

The report will serve as a status report of the engineering efforts, while providing background on the issues raised during the evaluation, and actions taken to resolve the issues. The containment radial shear issue is addressed in a separate Engineering Evaluation (Reference 5.38).

2.0 SCOPE The scope of this engineering Evaluation is limited to safety-related steel and concrete structures in the Units 1 and 2 containments of the Salem Nuclear Generating Stations.

3.0 DISCUSSION

3.1 BACKGROUND

The containment and the internal structures of SGS are designed for various loads and loading combinations as described in SGS-UFSAR, Section 3.8 and as shown in Attachment 7.1.

Design loads include internal pressure, P, and temperature effects, T and TL, which result from a number of postulated pipe rupture and loss-of-coolant (LOCA) events. Pipe ruptLJre events are based on occurrence of hypothetical failures in large pipes, such as a main steam line break (MSLB), and small pipe line breaks, while LOCA events include Double-Ended Pump Suction (DEPS) breaks, which are the current licensing basis. LOCA events due to the fuel upgrade/margin recovery program (FUMRP) DEPS break are anticipated to be a licensing basis in the near future, and needs to be considered in the evaluation. (Reference 5.1)

While the maximum pressures due to these transients are enveloped by the

  • original design basis requirements, the magnitudes of maximum temperatures increase from the original design basis temperatures.

2of20

S-C-ZZ-SEE-1048 Date: Februarv 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

Containment structures were originally designed for the maximum temperature at the uninsulated section of the liner of 246°F for loading Case C and 285°F and 306°F for load Cases B and A. respectively. The basis for these temperatures is not clear, but it is suspected that they are related to the temperature of saturated steam at the specified pressure.

Since the temperatures associated with the updated MSLB exceed the original design basis of the SGS containment structures, an engineering review of structural design calculations was performed to assess the impact on the design.

This report provides a status of the engineering review efforts and discusses various concerns raised during the review and actions taken or being taken to resolve these concerns.

3.2 DESCRIPTION

OF STRUCTURES

Concrete and steel internal structural systems are provided to either support these equipment and piping systems and/or to provide radiation protection to provide access for plant maintenance.

3.3 METHOD OF REVIEW Design calculations for containment structures described above were reviewed for an increase in design temperatures under accident conditions.

Engineering Evaluation S-C-ZZ-SEE-0825-1 (Reference 5.39) provides guidance for evaluation of structures subjected to thermal loadings.

Generally, accident thennal loads can be neglected if they can be shown to be secondary and self-limiting in nature. Only those structures which are highly restrained, and which have connection details which do not allow distortion need to be evaluated.

3of20

S-C-ZZ-SEE-1048 Date: Februa 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BR ATS ITEM:

Designs of the structures were reviewed for updated MSLB and LOCA events using the following methods.

1. The concrete containment structure, including the liner, was evaluated by performing a detailed review of the existing design calculations and the associated drawings. Impact of the increased temperature on the critical areas of the design were assessed, and the results were documented in a calculation (Reference 5.4).
2. For other strudures, such as steel structures within the containment (e.g., annular steel, steam generator platforms), drawings and associated design calculations, if any, were reviewed to detennine if the structural details would allow the structure to expand when

. subjected to the increased temperatures.

It was concluded that in a majority of the cases, thermal effects were secondary, and that lack of restraint of thermal expansion would allow the structure to accommodate increased temperatures without causing significant additional *stresses. Two areas of steel structures, however, required further evaluation and eventually physical modifications as discussed in Section 3.4.

3.4 REVIEW RESULTS 3.4.1 Concrete Containment Structure The concrete containment, including the liner, was evaluated for the pressure and temperature transients of Reference 5.1 and results were documented in Calculation 650-0791-004 (Reference 5.4).

The containment was originally evaluated in 650-0791 and 650-0591 (References 5.2 and 5.3). These calculations were reviewed to identify critical load combinations governing the stresses in reinforcing bars, concrete, and the liner, for the design loads including temperature and pressures.

  • 4of20

S-C-ZZ-SEE-1048 Date: Februa 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

a. Reinforcing Bars Load combination "A11 which includes 1.5P and 1.0T produced the maximum stress of 52.6 ksi in the hoop reinforcing bars at El. 140'-0".

The design basis pressure P used was 47 psi, while r' was taken to be 306°F, as described in Section 3.1.

A number (11) of combinations of pressures and temperatures associated with main steam line breaks were considered to determine the stresses in these reinforcing bars. Pressure varied from a high value of 45 psi to a low value of 27.3 psi, while temperatures varied from a high value of 351°F to a low value of 239°F. These temperature and pressure combinations were obtained from Reference 5.1.

It was concluded that the resulting stresses in the reinforcing bars in all areas due to the updated MSLB were enveloped by the original design stresses, with the maximum stress varying from 61% to 94% of the stress due to the original design temperature and pressure.

The evaluations were performed assuming* that the peak liner temperature is the same as the peak containment atmospheric temperature, and occurs at the same time as the peak pressure. This is conservative since Calculation 680-1800 (Reference 5.11) demonstrates that the predicated maximum average liner temperature is less than the maximum air temperature, and occurs at about the same time. However, the maximum pressures do not occur at the same time as the maximum temperatures. Hence, the stresses in reinforcing bars are anticipated to be lower than calculated.

Review of the design of the containment structure at the junction between the cylindrical shell and the mat uncovered a potential problem in the areas of the radial shear capacity of the cylindrical wall.

The evaluation of this area has been performed separately in more detail. (See Engineering Evaluation S-C.ZZ-SEE-1049, Reference 5.38) 5of20

S-C-ZZ-SEE-1048 Date: Februa 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

b. Liner The worst-<:aSe for the liner design is when the temperature is high and the pressure is low (compression), or when the pressure is high and the temperature is low (tension). In the original design, the liner has a maximum interaction ratio of .902 for load case Cat El. 120'-0".

Additional stresses in the liner due to increased temperatures cause the liner to yield and redistribute the stresses to the reinforcing bars.

Therefore, an evaluation of the reinforcing bars was performed to determine the containment structural adequacy. It was concluded that the amount of reinforcing bars is sufficient and that structure will function as designed. No issues requiring further engineering effort were discovered during this evaluation.

It was assumed that the insulated portion of the liner (below El. 110'-0'1 was not affected, since Calculation 680-1800 (Reference 5.11) demonstrates that the insulation limits the liner temperature in this region to below 13D°F, which is the liner temperature used as the basis of the original design.

3.4.2 Other Structures Other structures within the containment were reviewed using the method described in Section 3.3(2) above. These structures are listed in Attachment 7.2, along with the basis for the evaluation.

Based on this review, it was concluded that all structures, except the strudural steel reactor coolant pump access platforms and the containment spray pipe support steel have structural details which would allow them to expand under increased temperature without significant restraint.

Therefore, thermal stresses which are secondary in nature are small, and thus, the structures will function as designed when subjected to increased temperatures due to MSLB.

6 of20

S-C-ZZ-SEE-1048 Date: Februa 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

3.4.2.1 Containment Spray Piping Support Steel Containment spray piping is supported off of the dome liner of the containment structure. Details of the piping and supports are shown on References 5.12 through 5.19, while calculations which support the evaluation for increased temperatures are included as References 5.20 through 5.22. Connections of framing to the liner at three (3) locations were revised to allow axial movement, thus increasing the frame flexibility for thermal loadings and eliminating embedment and liner overload conditions. These modifications are documented in DCP 1EC-3450 (Reference 5.23).

3.4.2.2 Reactor Coolant Pump Access Platform Reactor coolant pump access platforms in Unit 1 and 2 are detailed in drawings listed as References 5.24 through 5.27. Because of restraining welded connections at two locations in each platform, thermal stresses due to increased temperatures could not be judged to be self-limiting and failure of these welds could not be eliminated as a possibility. These connections were modified to be sliding connections to relieve thermal stresses and thus qualify the platforms.

Design calculations for the structural evaluation of these platforms are listed as References 5.28 through 5.35. These modifications are documented in DCPs listed as 1EE--0134 and 2EE-0097 (References 5.36 and 5.37) for Unit 1 and Unit 2 1 respectively.

3.5 PRESENT STATUS Evaluation of various concrete and steel. structures in the containment has been completed, as described above.

All structures are qualified with planned minor modifications to the containment spray piping support steel and reactor coolant pump access platforms. The containment radial shear issue is being addressed separately.

7of20

S-C-ZZ-SEE-1048 Date: Februa 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS!TEM:

3.6 FUTURE PLANS Activities necessary to be completed are:

  • Issue all calculations listed in references.
  • Prepare calculations for those structures for which calculations could not be located.
  • Develop a resolution of the issue of containment radial shear.

4.0 CONCLUSION

S Based on the results of the evaluation of the containment structures for increased temperatures due to updated MSLB events, and limiting the conclusions to the issues addressed in this report, it can be stated that the impact on structures was minor and with these minor modifications in steel structures, structures can accommodate the increased temperatures and meet the design basis requirements of the plant. The issue of the radial shear design is addressed elsewhere.

5.0 REFERENCES

5.1 Memo from T. K Ross to R. H. Koch dated September 18, 1995, NFS 871; MSLB and LOCA Containment Integrity Analysis Information. (This memo contains temperature and pressure transients which were used to evaluate containment structures.)

5.2 Calculation No. 680-0791, Seismic Analysis of Containment Vessel, Conrad Associates, Van Nuys, California, February 26, 1970.

5.3 Calculation No. 680-0591, Containment Dorne, Cylinder, and Mat Design, RevisionO.

5.4 Calculation No. 6$0-0791-004, Revision 0, Evaluation . of Primary Containment Concrete for Latest Temperature Loads, Revision 0 5.5 Drawing 201108-A-8707-7, Dome -Plans and Sections 8of20

S-C-ZZ-SEE-1048 Date: Februarv 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

5.6 Drawing 201109-A-8707-3, Dome - Sections

5. 7 Drawing 20111 O-A-8707-5, Dome - Reinforcing Bar Schedule 5.8 Drawing 201125-A-8708-5, Development of Main Wall Design, Sheet 1 5.9 Drawing 201126-A-8708-5, Development of Main Wall Design, Sheet 2 5.10 Drawing 201127-A-8708-7, Dome- Steel Rings at Meridional Design 5.11 Calculation 6$0-1800, Revision 1, Temperature Profile of Concrete Containment Wall 5.12 Drawing 201181-A-8710, Revision 10, Dome Uner and Details 5.13 Drawing 223112-A-8989, Revision 1, Dome Uner Miscellaneous Supports -

Plan 5.14 Drawing 223114-A-8989, Revision 3, Dome Uner - MBC Sup[XJrts, Sections and Details 5.15 Drawing 223119-A-8989, Revision 3, Dome Uner, Miscellaneous Steel, Sheet2 5.16 Drawing 223121-A-8989, Revision 7, Dome liner, Miscellaneous Steel, Sheet2 5.17 Drav.ring 223123-A-8983, Revision 0, Dome Uner MBC Supports, Details 5.18 Piping Drawing 207466-A-8808, Revision 15, Containment Spray Piping -

Plan 5.19 Piping Drawing 207467-A-8808, Revision 16, Containment Spray Piping-Plan 5.20 Calculation No. 6$1-1710-002, Revision 0, Analysis of Modifications to the Containment Spray Dome Framing Steel, Unit 1 5.21 Calculation 681-1710, Revision 1, Containment Spray Dome Framing Steel, Unit 1 - MicasP/us 9of20

S-C-ZZ-SEE-1048 Date: Februa 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UP D MAIN STEAM LINE BREAK ATS!TEM:

5.22 Calculation No. 6$1-1710-001, Revision 0, Refined Analysis of Containment Spray Dome Framing steel, Unit 1 5.23 DCP 1EC-3450 5.24 Drawing 212370-A-887 4, Revision 11, Reactor Coolant Pump Access Platform, Unit 1, Sheet 1 5.25 Drawing 238140-A-1494, Revision 11, Reactor Coolant Pump Access Platform, Unit 1, Sheet 2 5.26 Drawing 212371-A-8874, Revision 12, Reactor Coolant Pump Access Platform, Unit 2, Sheet 1 5.27 Drawing 238145-A-1494, Revision 4, Reactor Coolant Pump Access Platform, Unit 2, Sheet 2 5.28 Calculation 6S1-1397, Reactor Coolant Pump No. 11, Steel Access Platform

- MicasPlus, Revision 1 5.29 Calculation 6$1-1406, Reactor Coolant Pump No. 12, Steel Access Platform

- MicasP/us, Revision 1 5.30 Calculation 681-1407, Reactor Coolant Pump No. 13, steel Access Platform

- MicasP/us, Revision 1 5.31 Calculation 651-1408, Reactor Coolant Pump No. 14, Steel Access Platform

- MicasPlus, Revision 1 5.32 Calculation No. 652-1423, Reactor Coolant Pump No. 23, Steel Access Platform - MicasPlus, Rev. 1 5.33 Calculation No. 682-1424, Reactor Coolant Pump No. 24, Steel Access Platform - MicasP/us, Rev. 1 5.34 Calculation No. 682-1421, Reactor Coolant Pump No. 21, Steel Access Platform - MicasP/us, Rev. 1 5.35 Calculation No. 682-1422, Reactor Coolant Pump No. 22, steel Acces5 Platform - MicasPlus, Rev. 1 10of20

S-C-ZZ-SEE-1048 Date: Februarv 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

5.36 DCP 1EE-0134 5.37 DCP 2EE-0097 5.38 Engineering Evaluation S-C-ZZ-SEE-1049 5.39 Engineering Evaluation S-C-ZZ-SEE-0825-1 5.40 DE-CB.CAN-0043(0), Configuration Baseline Document for Containment Internal Structures 6.0 IMPACT ON VENDOR TECHNICAL DOCUMENTS This engineering evaluation has no impact on any vendor technical documents.

7.0 ATTACHMENTS 7 .1 LOAD COMBINATIONS 7.2 INVENTORY OF STEEL INTERNALS STRUCTURES 11 of20

S-C-ZZ-SEE-1048 Date: Februa 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

ATTACHMENT 7.1 LOAD COMBINATIONS CONTAINMENT VESSEL

{a) S = D +/- 0.050+1.5P + (T +TL)+ B (b) s = D +/- O.OSD + 1.25P + (T' +TL')+ 1.25E + B (c) S = D +/- 0.050 + P + (T"+ TL") + E' + B (d) s = D +/- 0.050 + 1.1 Wt+ B + Wb (e) S = D +/- 0.050+1.15P + B Where:

s = Required capacity of structural member D = Dead Loads and Soil Pressure Loads E = Worst-case of either Operating Basis Earthquake Loads or Winds Load E' = Design Basis Earthquake Loads T = Load due to maximum temperature gradient through the concrete shell and mat based upon temperatures associated with 1.5 times accident pressure TL = Load exerted by the liner based upon temperatures associated with 1.5 times accident pressure r = Load due to maximum temperature gradient through the concrete shell and mat based upon temperatures associated with 1.25 times accident pressure TL' = Load exerted by the liner based upon temperatures associated with 1.25 times accident pressure T" = Load due to maximum temperature gradient through the concrete shell and mat based upon temperatures associated with accident pressure 12of20

S-C-ZZ-SEE-1048 Date: Februarv 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

TL" = Load exerted by the liner based upon temperatures associated with accident pressure wb = Bursting pressure loading associated with a tornado Wt  :::; Tornado Loading STEEL INTERNAL STRUCTURES

{a) s = D+L+l+H+C (b) s = D+L+l+H+E+C (c) s = D + L + I + H + E' + C (d) s = D + L + I + H +Wt+ C (e) s = D+L+l+H+P+J+C (f) s = D + L+ I + H + E' + P + J + C Where:

s = Required capacity of structural member or section D = Dead Loads and Soil Pressure Loads and Equivalent Uniform Commodity Loads L = Live Loads and Hydro Loads I = Impact loading ~ere a moving design load is present H = Thermal E = Worse case of either Operating Basis Earthquake Loads or Winds Load E' = Design Basis Earthquake Loads p = Pressure Loads J = Pipe Whip Load 13 of20

S-C-ZZ-SEE-1048 Date: Februa 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

ATTACHMENT 7.2 INVENTORY OF STEEL INTERNALS STRUCTURES

  • t~i~4£W.hl{~'-~.C.¥M~:::Y'..:'.::~* '.::Q.MYY.1~~\~*:.:;:~.'.i ~*'.: ;*;: :*~qA~~9..~~~9.N'.I:~t:::*~::* :::*,~,~~-~~*~*~.:~:: * ;.'.);:;:. : ;~:*: :.~:*,.:~;,:~. *:/f:')'

Columns - Elevations & 201191 681-1400 Modeled as part of Details 201186 681-1724 8LMP 201192 681-1725 217668 681-1726 219156 682-1439 240017 682-1727 227908 6$2-1728 227909 652-1729 Floor Framing El. 100' 201187 681-1400 Modeled as part of 217666 681-1724 SLMP 207068 6$1-1725 207071 681-1726 6$2-1439 6$2-1727 6$2-1728 6$2-1729 Floor Framing El. 130' 201188 6$1-1400 Modeled as part of 201195 681-1724 SLMP 217667 6$1-1725 217669 681-1726 207069 6$2-1439 207072 682-1727 652-1728 6$2-1729 Reactor Coolant Pumps 212370 6$1-1397 Thermal effects cause Access Platforms @ El. 212371 6$1-1406 problems at 1031-611 & 111' 238140 681-1407 connections.

238145 681-1408 682-1421 682-1422 682-1423 682-1424 14 of20

S-C-ZZ-SEE-1048 Date: Februarv 1996 TITLE: ~Vti LUA TION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

~fr§~m~~U.@¥r~~M~m;r.:u( ::tj~w!~~)(:~;=:::.~w ;!~£*=µ4.~-~$~:~;1(!'.\:::::;::: -~:$,~~:~~~~i:nx~~~n::::::.:;::;<~:::'.HiH~~

Steam Gen. Access 245765 681-1399 Modeled as part of Platforms @ El. 93' 246660 6S1-1412 SLMP 246663 681-1416 246664 6S1-1417 245940 681-1419 245941 6S2-1425 245942 6S2-1429 682-1433 682-1434 682-1436 Steam Gen. Access 250251 None No structural members.

Platforms @ El. 101' 250987 Platform consists of 250252 grating and toe plates 250988 supported from existing steel.

Steam Gen. Snubber 230693 None Platform supported by Service Platform @ 237068 members which have El. 125' slotted holes.

Missile Shield Access 237323 None Platform connections to Platforms and Fan Ties missile shield have slotted holes.

Steam Gen. Access 227921 681-1398 Modeled as part of Platforms @ El. 155' 227922 681-1410 SLMP. Steel platforms 227923 681-1411 supported on existing 681-1413 steel; everything grows 651-1414 during high 681-1415 temperature increases.

681-1418 651-1420 6$2-1426 682-1427 682-1428 652-1430 682-1431 652-1432 652-1435 682-1437 15of20

S-C-ZZ-SEE-1048 Date* Februarv 1996 TITLE: EVALUAIIO~ OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

~Y1~f~U~t9~~:~~M~*1:::~.\::}:.:i;:. '.:'.P.~wi.~:9:§;:;:};:=;;,:~~, :\;9~&~-4~ff§~m'.!'.~i*i-:: ':1:~~~¥.~N.!¥'.:X:D:*:~}~:~r::~;f?~::iFi.~:;;

Pressurizer Shielding & 219153 650-0560 Under investigation Access Platforms @ 212362 El. 130' 237963 238311 238197 223110 223111 237308 237309 241813 Steam Gen. Manway 201506 650-0203 Small platforms Covers Laydown 238138 constructed of angles.

Platforms 208910 Angle legs only attached to S.G.

support steel. No restraints in other directions. Platforms are okay.

Orbital Service Bridge 238127 650-0209 Slotted connections Access Platform @ 238128 exist.

El. 232' (Unit 2 only)

Missile Shield & 227915 None Similar to S.G.

Electrical Trays Storage platforms at el. 155'.

Area Platform @ El. 181' Platform and supporting steel both grow.

Polar Crane Platform 201516 None Platform supported Access to TV Camera from Polar Crane by angle hanger and diagonal brace.

Platform members have flexibility to move.

Reactor Pit Platforms & 208918 None Connections to Ladders concrete wall have slotted holes .

  • 16of20

S-C-ZZ-SEE-1048 Date: Februarv 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK ATS ITEM:

it~:f~f~V.¢.Xf:l~~:~U~M§~1;::~::::r;\: ;;~~*M~:1.::;.;:::::~:\:::;;:, :i::£~~tj4ij*-9~{i:{I~ .:~:~ :~:¢-~~~~~f~~.i ;i'.i~:::~::=:.;i;~Y:'.:~'.N;~!::~;1iW Misc. Steel Supports 223106 6S1-1400 Modeled as part of Below El. 100' 223107 651-1724 SLMP 223108 651-1725 223109 6S1-1726 227900 682-1439 227901 652-1727 227902 6S2-1728 240013 6S2-1729 240014 240015 Snubber Service 240016 None Not applicable.

Platforms Access Platforms consist of Ladders ladders only.

Ladder to Top of 246875 None Platform has slotted Pressure Relief Tank 600856 holes at the connection to the misc. steel below el. 1001*

Shielding Steel & Pipe 237316 680-0903 See Note2 Restraints 237317 681-0447 239787 681-0448 239775- 6S1-0780 239785 680-0904 240175 680-0905 240176 682-0916 240177 682-0917 240180- 6$2-0918 240187 682-0921 241225 682-0922 241226 682-0930 241227 240276 248830 Pipe Restraints (Unit 2 600243- None See Note 2 only) 600249 600253 248960 17 of20

S-C-ZZ-SEE-1048 Date: Februarv 1996

  • TITLE:

ATS ITEM:

EVALUATION OF STRUCTURES FOR INCREASED TEMPERATURES DUE TO UPDATED MAIN STEAM LINE BREAK 1:n~1~11~4M4:;~~~,~~'~!t:.~:::.:~:. '.-'P.AA\~i~N.?f:':~:;:::iP:~:: !i!q~4~~~~,~N!:;'.~':&Xi ::~9~~:~~Nt~~:.;:;~;::i:".'.:~:t::.~g:r_:.:~:t::\rH:;:f Feedwater Limit Stops 201196 680-0450 See Note2 201197 6S0-0451 217670 6$0-0452 217671 650-0453 217672 681-0757 219896 219897 Main Steam & Feedwater 219860- 680-0449 Evaluated by use of a Limit Stops 219863 MicasPlus structural 224360- analysis model.

224364 219879 238143 238144 Reactor Coolant Pump 208905 6$0-0424 Structure consists of Supports 208906 pin and pin hole 201320 connections at base support points.

Horizontal tie backs have gaps to permit movement.

Steam Gen. Supports 208903 650-0423 Structure consists of 208904 pin and pin hole 247392 connections at base 247393 support points.

Horizontal tie backs have gaps to permit movement.

Steam Gen. Horizontal 201502 6S0-0422 Structure consists of Stay@ El. 130' 201503 struts with "shock absorbers" and pin connections. Gaps at connection points are provided to permit movement.

18of20

S-C-ZZ-SEE-1048 Date: Februarv 1996 TITLE: EVALUATION OF STRUCTURES FOR INCREASED TEMPERATUR~S DUE TO UPDATED MAIN STEAM LINE BREAK

  • ATS ITEM:

.:: *:~ (*~~: ~~: ~:-. ;*.? :-:::::~*: ;.-:~:* :~"* ~. *:; .= *;

f:::,;:;:§~v~::i9~::~~f.M~~r:f;~:~:::;:,::* {~~~~~~.:::}:*~:s:::.~:; ~-CALCUl.:ATION**,*~*:.:*:,~: :;jg9,¥M~~fS,::;;.~::}:::i:i('.EJ!*I:;'.::.f.)'.!::~I
  • ~T

";,.,.  : .. -:- .... " : J ******* ..... "=" -=* :: . *.*.:...:. ,:, : :~

Pressurizer Supports 208907 6S0-0418 Provisions exist for 238092 650-0422 expansion of the 240044 structure.

Containment Liner 201175- 650-0591 Modeled as part of 201182 6S0-0417 SLMP. Problems exist 201198 650-0766 due to thermal.

201199 681-1710 201275 204778 208915 602430 Dome Liner Misc. 223118- 6$0-0213 Modeled as part of Supports 223121 SLMP. Problems exist 223123 due to thermal.

223112 223114 Reinforced Concrete See Note 3 See Note 3 Concrete structures are Internal Structures inherently slow in response to temp.

changes due to poor thermal conductivity.

MSLB elevated temperatures exist for a relatively short duration.

NOTES:

1. Calculations listed are those applicable to the structure listed.

These calculations do not necessarily address the effects of thermal loading.

2. Pipe rupture restraint and shielding structures need not be reviewed for high thermal effects. These structures perform their function before the extreme accident temperature of 351°F can be reached in the containment.
3. For calculation and drawing references see page T4-1 of
  • Reference 5.40.

19of20

ATS ITEM:

8.0 SIGNATURES

~ 'C. ~gkY Originator

~ J. ~ lt--Zl-'/t Programmatic Spa~

Supervisor 20of20

Retrieved from "https://kanterella.com/w/index.php?title=ML18102B020&oldid=2505456"