ML23291A404

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1 to Updated Final Safety Analysis Report, Chapter 6, Appendix 6A, Subcompartment Differential Pressure Considerations
ML23291A404
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Issue date: 10/12/2023
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SSES-FSAR Text Rev. 58 FSAR Rev. 64 6A-1 APPENDIX 6A SUBCOMPARTMENT DIFFERENTIAL PRESSURE CONSIDERATIONS Differential pressure analyses were performed for the reactor vessel shield annulus and the drywell head region.

The RPV shield annulus, which is 48.95 ft high and 1.70 ft wide at the top, has the 28 in.

recirculation pumps suction lines passing through it. The mass and energy release rates from a postulated recirculation outlet line break constitute the most severe transient in the reactor shield annulus. Therefore, it is selected as the pipe break when analyzing loading of the shield wall and the reactor pressure vessel support skirt for pipe breaks inside the annulus. Estimation of mass and energy release is based on the guidelines set forth in GEs letters to Bechtel; (GB 78-14 dated January 16, 1978 and GB 78-24 dated January 27, 1978) and Technical Description Annulus Pressurization Load Adequacy Evaluation (NEDO-24548/78 NED 302).

The subcompartment differential pressure analysis inputs and results presented in this section for the annulus pressurization analysis and the drywell head pressurization analysis are based on the original design basis conditions unless otherwise noted. The blowdown mass and energy release data for the recirculation outlet line break at power uprate conditions has been reanalyzed. The analyses performed for power uprate concluded that the original analyses were conservative and bound power uprate conditions. The original analysis for drywell head pressurization was judged to be overly conservative with respect to power uprate conditions and no reanalysis was performed.

Therefore, the design of the shield wall and refueling seal plate is not affected by power uprate.

Recirculation Outlet Line Break Table 6A-1(a) presents the mass and energy release data estimated by applying the NEDO 24548 method of combining blowdown data calculated from finite and instantaneous break opening time approaches. The blowdown from the supply side is assumed to be released into the annulus due to the break being located in the reactor shield wall penetration. The break is postulated to occur at the nozzle safe end attachment weld to the pipe. The blowdown from the vessel side is vented into the drywell atmosphere. Table 6A-1 (b) provides, as a function of time, the mass flux and areas used for each side of the break. Some physical parameters pertinent to the blowdown rate estimation are noted in the table.

SSES-FSAR Text Rev. 58 FSAR Rev. 64 6A-2 Feedwater Line Break In addition to the analyses for the recirculation outlet line break in the annulus, similar analyses using the same methodology for blowdown rate estimation are performed for a postulated feedwater line break in the annulus. Table 6A-1(c) presents the mass and energy release rates generated by only applying the very conservative instantaneous break opening time method.

The blowdown from the supply side is assumed to enter the annulus due to the location of the postulated break being situated inside the reactor shield wall penetration. The blowdown from the vessel side is released into the drywell. The analysis conservatively assumes that the blowdown from both sides enters the annulus region. The mass flux as a function of time and areas used for each side of the break are presented in Table 6A-1(d). Some pertinent physical parameters are noted in the table.

In addition to the above mentioned lines, there are recirculation inlet lines inside the annulus. Since the recirculation inlet lines are much smaller than the outlet lines, the expected annulus pressurization would not be as severe as for the outlet lines, thus the inlet lines were not analyzed.

Note that the most restricted flow area on the feedwater supply pipe side is the break area itself.

Full break area steady state blowdown from this side is conservatively assumed to be reached immediately after the pipe rupture. Note that only the very conservative instantaneous break opening time is used in the generation of Table 6A-1(c) and 6A-1(d) data.

Head Spray Line In considering the drywell head region, the maximum blowdown rate stems from a break in the RHR head spray line. The blowdown mass and energy release rates for this line are calculated using Moody Critical Flow of 2700 lbm/sec-ft2 and an enthalpy of 1198 Btu/lbm. Table 6A-2 shows the blowdown schedule for a 6 in. schedule 80S line break with an effective break area of 0.181 ft2.

Since this line could singularly pressurize the drywell head region, it is chosen for analysis in a postulated break.

The annulus pressurization and drywell head pressurization analyses were performed using Bechtels COPDA computer code. These adjusted pressures are combined with the other appropriate loads (eg, seismic and jet impingement) to develop design loads for the affected structures and components. Subcompartment venting is used to ensure that the differential pressures developed will remain below the structural capability of compartment walls.

BIOLOGICAL SHIELD ANNULUS SUBCOMPARTMENT MODELING PROCEDURES AND ANALYSIS Biological Shield Annulus An analysis of the pressure distribution around the reactor pressure vessel after a recirculation outlet line break was performed. The general layout of the shield annulus is shown on Dwgs. C-331, Sh. 1, C-371, Sh. 2, C-1932, Sh. 3, C-1932, Sh. 4, and C-1932, Sh. 5, Figures 6A-1(a) and 6A-1(b). Figure 6A-2 is a schematic of the RPV shield annulus model.

The model consists of six major levels. Each level is subdivided into twelve 30° segments to form a total of 72 nodes inside the annulus plus an additional node for the rest of the drywell.

SSES-FSAR Text Rev. 58 FSAR Rev. 64 6A-3 In general, the arrangement of the pipes in the annulus determines the most representative level division, since they constitute the only significant flow restrictions. This 73 pressure node model is considered detailed enough to conservatively predict the maximum pressures on the compartment structure. Therefore, a nodalization sensitivity study is not needed.

For the purpose of determining peak pressure in the reactor vessel shield annulus, all insulation was assumed to move flush against the biological shield wall while still maintaining its original thickness. The volume of the insulation is excluded from the net volume of each subcompartment, and the projected area of the insulation which blocks the venting path is also excluded from the free venting area used in the analysis.

The major vent path to the drywell atmosphere is through the top of the biological shield annulus.

Venting through the shield wall is allowed only through the ventilation duct openings at the lower section of the shield wall.

Initial conditions used in this analysis are 15.45 psia, 135°F, and 30 percent relative humidity.

Tables 6A-3 and 6A-4 give the subcompartment volumes, flow areas, L/A ratio, and flow coefficients (including origins) used in the analysis.

The resultant pressure distributions are shown on Figures 6A-3a, 6A-3b, 6A-3c, 6A-3d, 6A-3e, and 6A-3f for the recirculation outlet line break and Figures 6A-3g, 6A-3h, 6A-3i, 6A-3j, 6A-3k, and 6A-3l, for the feedwater line break. The subcompartment pressure existing in each subcompartment at the time of peak differential pressure across the RPV are also shown on these figures. The reactor shield wall is designed for a uniform internal pressure of 70 psig. See Section 3.8.3 for description of the design of the reactor shield wall. COPDA was used to calculate the pressures while the plots were generated using a pre-processor (ABS-PLOT) and TEKPLOT.

Additionally, the load forcing functions which include both peak and transient loadings on the RPV and the reactor shield wall are presented on Figures 6A-7 and 6A-8 for the recirculation outlet line break and on Figures 6A-9 and 6A-10 for the feedwater line break. FORCE-GE was used to calculate the forces for the recirculation outlet line break and Bechtel Code NE698 for the feedwater line break while the plots were generated using a pre-processor (ABS-PLOT) and TEKPLOT. This forcing function represents the time-dependent resultant force on the structure and originates from the vector sum of the product of compartment pressure and area for each of the geometry nodes used to represent the surface.

For the recirculation outlet line break the 73 pressure node model is transformed into an 84 geometry node model for calculating the resultant forces. The geometry node model adds another level subdivision but uses the same arc segments. This allows better modeling near the recirculation line nozzle. The locations of the center of each node are given in Table 6A-5. For the feedwater line break the 73 pressure mode model is also used for the force model.

SSES-FSAR Text Rev. 58 FSAR Rev. 64 6A-4 The components of these nodal areas are calculated in the following manner:

(Ax)i

=

RiHi (Sin 1 i - Sin 2 i)

(Ay)i

=

RiHi (Cos 2 i - Cos 1 i)

(Ax)i, (Ay)i

=

x and y area components for node I Where Ri

=

Radius of the ith geometry node, in.

Hi

=

Height of the ith geometry node, in.

1 i

=

Starting angle (degrees) for ith geometry node 2

i

=

Ending angle (degrees) for ith geometry node For the recirculation outlet line break the resultant areas for each geometry node for the RPV are given in Table 6A-6. For the feedwater line break the resultant areas for each node are given in Table 6A-7. For the bio-shield the node areas are the ratio of the bio-shield radius divided by the RPV radius (12.7917/11.0937 = 1.1531) multiplied by the RPV nodal area.

Therefore, the force generated by a pressure, pi, acting on a nodal area Ai has the following components:

(Fx)i

=

Pi(Ax)i (Fy)i

=

Pi(Ay)i Where (Fx)i, (Fy)i

=

x and y force components acting on node i Pi

=

pressure acting on node i The compartment pressure transients resulting from a break in the reactor shield annulus generate a nodal force distribution over exposed surfaces. The resultant of this nodal force distribution is presented in Figures 6A-7, 6A-8, 6A-9 and 6A-10. There are no external moments generated by this pressure response. However, any moments would result from the application of the external force distribution to a structural model. This would generate shear stresses (leading to internal moments) due to bending of the elements used to represent the structure as a result of the non-uniform load distribution. Further discussion of this result is contained in Section 3.8.3 where the application of these annulus pressurization results is described in detail.

SSES-FSAR Text Rev. 58 FSAR Rev. 64 6A-5 Blowdown jet loads which include jet impingement and reaction forces against the reactor vessel are also analyzed for reference and comparison. Note that these analyses are based on the very conservative assumptions that the first pipe restraint nearest the nozzle fails. For the feedwater line break, approximately 9.5" pipe center line offset limited by the shield plug opening produces a net break area of 88.53 in², which, consequently, results into a total maximum jet load of 335,600 lbs.

against the vessel. These blowdown jet loads are relatively small compared with the peak load contributed by the unbalanced reactor annulus pressurization due to the same breaks.

Subcomponent Annulus Pressurization Loads - Major Project Improvements Initial Stretch Power Uprate (SPU) & Turbine Retrofit Project (TRP)

An evaluation was performed to analysis the impact on subcompartment annulus pressurization loads for the Stretch Power Uprate (SPU) and Turbine Retrofit Project (TRP) conditions.

A more realistic blowdown mass and energy release profile for RSLB was determined using the RELAP4 MODS computer code. The mass and energy release rates are provided in Table 6A-8.

These release rates were calculated using the same physical model as previously described in the licensing analysis section. The results of the RELAP4 analysis yield peak forces on the reactor vessel that are approximately 90% of the original peak forces. Thus, is can be concluded that the original analysis for the reactor annulus differential pressures and resultant reactor vessel and biological shield wall load forcing functions is bounding.

For the FWLB, the blowdown from both sides of the break increases for SPU and TRP. As stated previously with regards to the FWLB, only the supply side blowdown enters the annulus region.

Using the approach, the supply side blowdown for SPU/TRP is less than the total blowdown used in the original analysis; therefore, the previously analyzed loads were bounding.

Maximum Extended Lad Line Limit Analysis (MELLLA)

An evaluation was performed to analysis the impact on subcompartment annulus pressurization loads for operation in the Maximum Extended Load Line Limit Analysis (MELLLA) reactor operating domain.

A more realistic blowdown mass and energy release profile for RSLB was determined using the GE code LAMB for the AP load analysis. The LAMB code considers the pipe break separation time history, but ignores the fluid inertia effect, providing conservative results. This code analysis was accepted by the NRC during the licensing application. LAMB results at the minimum pump speed condition are bounded by the Susquehanna original analysis.

For the FWLB, the blowdown, as indicated by the flux of steam flashed from the mass blowdown, is bounded by that at the rated MELLLA power condition.

Extended Power Uprate (EPU)

An evaluation was performed to analyze the impact on subcompartment annulus pressurization loads with an increase in reactor thermal power at Extended Power Uprate (EPU) conditions.

For the RRLB, the analysis and conclusions reached for MELLLA domain remain valid.

SSES-FSAR Text Rev. 58 FSAR Rev. 64 6A-6 For the FWLB, the blowdown from both side of the break increases for SPU and TRP. As stated previously with regards to the FWLB, only the supply side blowdown enters the annulus region.

Using this approach, the supply side blowdown for SPU/TRP is less than the total blowdown used in the original analysis; therefore, the original analyzed loads are bounding.

DRYWELL HEAD REGION SUBCOMPARTMENT ANALYSIS The design basis pressure differential between the drywell head and containment region is a structural requirement of the drywell head. A pressure analysis of the drywell head region for a postulated head spray line break was performed.

Figure 6A-4 illustrates the basic arrangement of the head region. Venting from the head region is accomplished through ventilation openings as shown on Figure 6A-4. These vent openings provide a total of 16.75 sq. ft. vent area with an equivalent orifice (slightly rounded) discharge coefficient of 0.67 to relieve pressure build-up caused by the postulated break.

Figure 6A-5 is the schematic flow diagram with vent flow areas and discharge coefficient used in the drywell head venting analysis.

To determine peak pressure in the drywell head, all insulation was assumed to remain in place.

Initial conditions of 15.4 psia, 135°F, and 20 percent relative humidity were used in this analysis.

The pressure transient of this analysis is presented on Figure°6A-6. It can be seen that the maximum pressure in the drywell head region is 23.2 psia and occurs 0.83 seconds after the head spray line break. Considering the containment pressure to be atmospheric (no drywell air displaced into the containment), a drywell head to containment pressure differential of 8.5 psid is obtained. This pressure differential is well below the design pressure differential of 16.0 psid.

SSES-FSAR

.U!tlL~A=11~L RF~CTOP PRIMARY SYSTEM BLOWDOiN PLOW ~ATES AND FLUID ENTHALPY -

RECIRCULATION OUTLET LINE BREAK Tim~

Mass Flow Enthalpy l§~gl J!bmLfi!Ha J~iYLl~.ml

o. 000 0.0000 0.000
2. 5500- 03 1.3400+03 527.9 J. gooo-03
2. 6 750+ 0]

527.9

4. 9600-03 4.0100+03 527.9 5.8600-03 5.3500+03 527.9
7. 3 700- 0) 8.0200+03 527.9 9.2400-03
1. 2025+ 04 527.9
1. 1800-02 1.9285+04 527.9 1.3800-02
2. 6 560+ 04 527.9
1. 5800-02 3.2355+04 527.9 1.. 8000- 02
4. 5975+ 04 527.9 2.oeoo-02 Q.5975+04 527.9 2.0800-02 2.2400+04 527.9
2. 1800- 02 2.4130+04 527.9 2.2800-02 2.5840+04 527.9
2. 3800-02 2.7520+04 527.9 2.5800-02 3.0780 04 527.9
2. 7 800- 02 3.3880+04 527.9 3.0800-02 3.8170+04 527.9 3.5800-02 4.4220+04 527.9
3. 7 000-02 4.5975+04 527.9
4. 1 q 00-0,
4. 5 975+ 04 527.9 4.1400-01 3.4370-+04 527.q 1.0000+00
3. 4 370+04 527.9 Rev. 35, 07 /84

SSES-f'SAP.

RECIFC. OUTLET LINE BREAK BLOWDOWN MASS FLUX TINE HISTOFY 0.00255

o. 004(}6 0.00737 0.01180 0.01580 0.02080 0.02081 0.02180 0.02380 0.02780 o.. 03580 0.03700 0.41400 0.41410 1.0 21200 21200 21200 21200 21200 21200 8410 8410 StHO 8410 8410 8410 8410 8410 8410 ve~sel_Side Effective

~r~~i-A.r.:~~-J.H.!l 0.0316

o. 096Q 0.1892 0.4548 0.7631
1. 0843
i. 3 317 1.4346

,. 6361 2.01q2

2. 6290
2. 7 333
3. 6fi40
3. 6Q40
3. 6440 0.00255 21200 0.0316 0.00496 21200 O.Og6q 0.00737 21200 0.1892 0.01180 21200 0.4548 0.01580 21200 0.7631 0.02080 21200 1.0843 0.02081 8410 1.3317 0.02180 8410 1.4346 0.02380 8Ul0 1.6361 0.02780 8410 2.01~2 0.03580 8410 2.6290 0.03700 8410 2.7333 0.41400 8410 1.8220 0.41410 8410 0.4420 laO __. __________. ______ SQlQ ___________________________ Q.4420 _________ _

NOTE: ListP.d below are pertinent physical ~~rameters use~ in thP blovdown estimation.

A= 3.644 ft2 D = 2.154 ft ho= 527.85 Btu/Lbm Li= 2.917 ft Po = 1031. 2 psia Psa t = 908 psia V = 0.02127 ft 3 /lbm Vi= 135 ftl Rev. 35, 07/84

!iniaum cross-sectional area between vess~l and break Pipe I.D. at the break location Vessel enth~lpy Inven+:.orv length Vessel pressure Saturation pressure Specific volome of ~he fluid initially in the pif>e Inventory volum+?.

0 o. 0 001 0.0207 0.0208 1.0 SSES-FSAR 1:!~Lt_§!=1J£l REACTOR PRI~ARY SYSTE~ BLOWDOWN PLOW RATES AND PLUID ENTHALPY -

PEEDVATER LINE BREAK 0

21830 21830 20075 20075 Enthal~IJBtuLlbmt 361.1 361.1 361.1 361.1 361.1 Rev. 35, 07/84

SSES-FSAR TABLE 6A-1 (d)

FEEDWATER LINE BREAK SLOWDOWN MASS FLUX TIME HISTORY Page 1 of 1 Ves§~I Sid~i.

Time (sec)

Mass Flux (lbm/sec/Ft2)

Effective Break Area {Ft2) 0.0001 20625 0.3528 0.0207 20625 0.3528 0.0208 20625 0.2679 1.0 20625 0.2679

§ui;mly Ei~!i! Sig~ m {~);

0.0001 20625 0.7055 1.0 20625 0.7055 NOTES:

( 1) The most restricted flow area on the feedwater supply pipe side is the break area itself. Full break area steady state blowdown from this side is conservatively assumed to be reached immediately after the pipe rupture.

(2} Listed below are some pertinent physical parameters used in the blowdown estimation:

AL = 0. 7055 ft2 Minimum cross-sectional area - supply pipe side D== 0.9478 Pipe I.D. at the break location ho ~ 361.1 Btu/Lbm FW enthalpy Po== 1053 PSIA Vessel pressure Psat = 213 PSIA Saturation pressure v = 0.01846 ft3/Lbm Specific volume of the feedwater vi = 2.79 ft3 Inventory volume (3) Annulus pressurization is based on blowdown flow from the supply side only. Based on the break locationf flow from the vessel side is expected to exit directly to the drywell.

Rev. 5.2, 11/97

TimP J§~fl o.o 20.0 SS'FS-FSAR TABLE_fiA-2 HEAD SPRAY LINE BREAK<l>

Staam Flow 1!!?mLf1~l-490 4 90 Steam Enthalpy

__ lD!YLl~ml __ _

1198 1198

<1 > Read sprav line break is based on 6 in. Schedule 80S pipe with Moonv Blowaown correspondinq ~o 2700 lbm/sec-sq ft.

Overall con~ainm~nt response is that of a "small break acci~ent".

Rev. 3 5, O 7 / 8 4 I

  • SSES-FSAR Paqe 1

. SUSQUEHANNA-COMPARTMENT VOLU~ES USED IN REACTOR VESSEL SHIELD ANWULUS SUBCO~PABT"RNT ANALYSTS CO"PAP.TftENT NO.

2 3

q 5

6 7

8 9

10 11 12 13 14 15 16 11 1A 19 20 21 22 2 :I 24 25 26.

27 28 29 30 31 32 33 34 35 Jfi*

37 38 39 40 41 Rev. 3 5, O 7 / 8 4 DESIGNATION V1 V2 VJ V4 V5

'V6 V7 V8 V9 V10 Y11 V12 V13 V14 V15 V16 V17 V18 V19 V20 Y21 V22 V23 V24 V25 V26 V27 V28 V29 V30 VJ 1 V32 V33

  • v34 VJS Y36 V37 V.18 VJ9 V40

,,, 1 VOLUf-!E, ft 3 54 54 54 54 54 5q 5q SQ 54 54 5q sci 69 76 15 76 16 69 69 76 75 76 76 69 59 57 57 57 57 57 57 57 57 57 57 59 60 58 60 76 58

. I

SSES-FSAR Paqe 2

!A§11;_§!=J

. ~USOUEHANN~-CO"PARTHENT VOLU"RS USED IN FEACTOR VESSEL SHIELD

-~NNUlUS SUBCO~PAPT~ENT -ANALYSIS COMPAPTMENT NO.

42 113 45 46 en 48 Q9 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 6q 70 71 72 73 Rev.. 3 S, 0 7 / ~ 4 V" 2 V43 V44 V45 Vll6 V47 V48 yq9 V50 vs, V52 V53 y5q VS5 V56.

V57 V58 V59 V60 V61 V62 V63 V6Q V65 V66 V67 V68 V6Q V70 V71 V72 V73 VOL0f'1E, ft' 60 76 58 60 76 58 60 77 71 73 77 75 77 77 74 77 73 71 77 "34 34 34 34 3Q 34 34 34 3ft 34 34 3Q 235200

SSES-FS~R SUSOUEH~NNA -

FLOW AREA AND COEFFIC!ENTS USED IN RF~CTOF VESSEL SHIELD ANNUlUS S0BCOMPARTMENT ANALYSIS Flow raths 1-2,1-12, 2-3, 3-4, 4-5, 5-6, 6-7.7-8, a-9.~-,o, Flow Area (ft. 2) 10- 11, 11-1 2 10 1-13,2-14, 3-J s, 4-16, 5-17,6-18, 7-19,A-20, 9-21,10-22,

,i-23,12-24 8.5 2-73.3-73, 5-73.6-73, e-1~,q-13, 11-73,12-73 2

13-2q, 18-19 9.5 13-14, 1 5-1 6, 16-17,17-18, 19-20,20-21, 22-23,23-24 13 14-15, 21-22 13-25,18-30, 19-31.24-36 14-26,16-28, 17-29, 20-32, 22-34,23-35, 15-27, 21-33 Rev. 35, 07/84 12 4.5 4.5 K

Factor

0. 13 1.0 0.05 1.0 0.42
1. 0
0. 13
1. 12

,

  • 0 0.13 0.1

,.o

0.,
0.,

0.13

1. 0 1.35 0.28
1. Q 0.28 0.2f3 1.0 0.28 0.2A 0.11

,

  • 0 l/A Flo v De.set i Pt ion (ft-l)

Co-ef f ic i~ nt 30° Turn final F:xpan~ion Friction Final Expansion Con t.ract ion Final 'P!xpansion 30° Turn Around Pip~

Fina 1 ~xp ans ion 30° Turn Around Pipe Final Expans:.on l\\round Pipe 0.62 1.01 0.73 0.54 0.43 Around Instrumr.t Pipe 30° Turn Final ~xpansion o.q3 Around Pipe Aron1'd Pipe Final Ex pans ion

~rour.d Pipe Around Pipe Fin a 1 ~xp ~nsion Around ~ipP Around Pipt?

Aro_u~d Pio~

Final Expansion

1. 57

,.11 0.94 0.97 0.83 0.66 0.9 0.86 0.61 o.e

0. 7 3

Flov Pa t.h s 25-36, 30- 31 11 25-26,26-27, 27-28, 28-29,.

29-30,31-32, 32-33, 33-3U, 34-35,35-36, 9.5 25-37,26-38, 2 7 ~ 3 9, 2 8-LI O, 29-41,30-42, 31-ti3,32-4U, 33-45,34-46, 35-47,36-qP, A.5 37-48,38-39 41-42, 4 s-4 6 37-38,40-41, 10.5 44-4s,u1-ns 9.S 3~-40,.42-43, 43-44,46-rn 11 37-49, 48-60 3 8-5 0, Q 1 - 5 3,

f44-56,~7-59 39-51,U2-S4, 45-57 40- 52, 4 3-55 U6-58 uq-so 59-6 0 Rev. 35, 07/84 8

6 8.5

11. 5 SSES-FSAR K

Facto~

o. 13
1. 0 0.13 0.16
1. 0 0.07

,.o

o. 13 0.01

,

  • 0 0.13
0. 16 1.0
0. 13
1. 0 o.o, 0.07
1. 0
1. 11

,

  • 0 0.08 1.0 0.07 1.0
0. 13
0. 15
0. 15
1. 0 L/A Flo v Description

( ft-1) c oe ff ic i e nt 30° Turn Final Expansion 300 Turn Around Pipe Fina 1 Expansion Friction Pinal Expansior, 30° Turn o.ss 0.58 Around Instrument Pipe Final Expansion 0.55 30° Turn Around Pipe Final Expansion 300 Turn Final Expansion 0.57 0.55 Around Ir.st rumen t. Pipe Friction Final Expansion 1.07 Around Pipe Final Expansion

,.14 A:-ound Tnstr 11m?.nt Pipe Final Expansion 1.07 Around Pipe Fin~ 1 Expansior:

30° Turn A!'our,d Pipe Around Pio~

Final Ex pans ion

1. 06 0.46 0.94 O.AB 0.96 0.88 0.94 0.96 0.68 0.96 O.R3

SS ES-FSJ\\i1 TABLF._6A-ij_Jcontinuedl (3 of Q)

Flow Ar~a K

Flow Pat'hs ff ti).

Factor 49-60 14 50-51 10.s 51-52,52-53, 56~57 13 54-55

14. 5 ss-56 10.s 58-59 11 4 9-61, 5 2-6 4,

53-65,55-67, 57-69 6.5 54-66, 60-72 56-68 61-62,63-64 67-68,69-70 71-72 Rev. 35, 07/84 6

5.5 5

0.125 0.01

1. 0 0.13 0.01 0.47

,.o 0.13 0.15

1. 0
o. 13 0.01
0. 15
1. 0 0.13 1.0
o. 13
0. 15
o. 12 o.,s 1.0
0. 13 O.U7
1. 0 0.49
1. 0 0.49 0.08
1. 0 0.49
0. 17 1.0
0. 11 0.96
1. 0 L/A Flow Description

( ft - 1) co~ ff ic i e nt

~0° Turn Around Instrumen~ Pipe Fir.al Expansion 0.42 30° Turn Arouni Instrumqnt Pip~

Around Pip'?

Final Expansion 0.48 30° Turn Around Pine Final Expansion 30° Turn Around Around Pinal Expansion 30° Turn Final Expansion 30° Turn Around Pipe Around CRP Around Pipe Fir.al 'Expansion 3C 0

'!'urn Around Pir,e Final ~xpansion Around Piot',

Final F:xpa n3 i C'n Around Pip<?.

0.45 0.42 0.5

o. 96 Around Instrumen~ Pipe Final Exoansion 1.0 Arou!ld Pipe Around CP.O Final Ex pans ion 300 Turn Around Pip~

Final :xp.usior.

1. 07 1.03 0.78 0.88 0.88 0.94 0.8 0.79 0.81 0.11 0.69

'f'low Pa1:hs 61-i 2, 6 2-6 3 64,65,66-67 flow Area (ft 2 )

6~-69,70-71 6.5 65-f.6, 71-62 4.5 61-73,63-73 6 Q-7 3, 6 6-7 3 67~73.,69-73 70-13, 72-7 3 62-73,65-73 68-73,71-73 Rev. 35, 07/84 6

7.5 SSES-FSAR K

Factor

0. 11 1.0 0.11 0.96 0..,

1.0 0.12 1.0 o.os

,.o Dgscr ipt ion JOO Turn Final Expansion 30° Turn Around Pip~

Around Instrum.ent Final Expansion contraction Final f:xpansion contraction Final Exp ans ion L/A Flov (ft-l)

Coe f fie ient:

0.9 0.94 Pipe 1.1 0.67 0.28 0.94 0.28 0.97

SSES-FSAR

- TABLE 6A-5 Geometry Node Locations Node Numbers Elevation

  • 1 - 12 733' 4-13/16" 13 - 24 740' 7"

25 36 745' 1/2" 37 48 751' 4~7/8" 49

~ 60 759' 4-5/8" 61 72 766' 1/4

73 - 84 773' 1/2" Node Angles Node Numbers 345° 1, 13, 25, 37, 49. 61. 73 315° 2, 14, 26, 38, so, 62. 74 285° 3, 15, 27, 39, 51, 63, 75 255°

4. 16, 28, 40, 52, 64. 76
r.

225°.

s, 17, 29, 41, 53, 65, 11 195° 6, 18, 30, 42, 54, 66, 78 165° 1, 19, 31, 43, 55, 67, 79 135° 8, 20, 32, 44, 56, 68, 80 105° 9, 21, 33, 45, 57, 69, 81 75° 10, 22 *. 34, 46, 58, 70, 82 45° 11, 23,. 35, 47, 59, 71, 83 15° 12, 24, 36, 48, 60, 72, 84 Note:

Elevations and node angles are for center of geometry nodes.

Rev

  • 3 S, O 7 / 8 4
  • Geometry SSES-FSAR TABLE 6A-6 RPV GEOMETRY NODE AREAS FOR RECIRCULATION OUTLET LINE BREAK Area (x) (inch2) based Area (y) (inch2) based Node Number on RPV (inside) radius on RPV (inside) radius 1

5741 1541 2

4209 4209 3

1541 5749 4

1541 5749 5

4209 4209 6

5749 1540 7

5749 1541 8

4209 4209 9

1541 5749 10 1541 5749 11 4209 4209 12 5749 1541 13 5724 1534 14 4191 4191 15 1534 5724 16 1534 5724 17 4191 4190 18 5724 1534 19 5724 1534 20 4190 4191 21 1534 5724 22 1534 5724 23 4190 4190 24 5724 1534 25 2596 696 Rev. 54, 10/99 Page 1 of 2

Geometry SSES-FSAR TABLE 6A-6 RPV GEOMETRY NODE AREAS FOR RECIRCULATION OUTLET LINE BREAK Area (x) (inch2} based Area (y) (inch2) based Node Number on ~PV (inside) radius on RPV (inside) radius 26 1900 1900 27 696 2596 28 696 2596 29 1900 1870 30 2596 690 31 2596 690 32 1900 1900 33 696 2596 34 696 2596 35 1900 1900 36 2596 696 37 6373 1708 38 4666 4666 39 1708 6373 40 1708 6373 41 4665 4665 42 6373 1708 43 6373 1708 44 4666 4666 Rev. 54, 10/99 Page 2 of 2

Geometry Mode Number 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Rev. 54, 10/99 SSES-FSAR TABLE 6A-7 RPV GEOMETRY MODE AREAS FOR FEEDWATER LINE BREAK Area (x) (inch2) based Area (y) (inch2) based on RPV (inside) radius on RPV (inside) radius 5749 1541 4209 4209 1541 5749 1541 5749 4209 4209 5749 1541 5749 1541 4209 4209 1541 5749 1541 5749 4209 4209 5749 1541 8320 2229 6091 6091 2229 8320 2229 8320 6091 6091 8320 2229 8320 2229 6091 6091 2229 8320 2229 8320 6091 6091 8320 2229 6373*

1708 I

\\

Page 1 of 2

Geometry Mode Number*

26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 Rev. 54, 10/99 SSES-FSAR TABLE 6A-7 RPV GEOMETRY MODE AREAS FOR FEEDWATER LINE BREAK Area (x) (inch2) based Area (y) (inch2) based o~ RPV (inside) radius on RPV (inside) radius 4666 4666 1708 6373 1708 6373 4666 4666 6373 1708 6373 1708 4666 4666 1708 6373 1708 6373 4666 4666 6373 1708 6373 1708 4666 4666 1708 6373 1708 6373 4666 4666 6373 1708 6373 1708 4666 4666 Page 2 of 2

SSES-FSAR TABLE 6A-8 REACTOR PRIMARY SYSTEM BLOWDOWN FLOW RATES AND FLUID ENTHALPY - RECIRCULATION OUTLET LINE BREAK POWER UPRATE VALUES Time (sec)

Mass Flow Enthalpy (lbm/sec)

(Btu/Ihm) 0 0.00 0.00 1.000-03 3.2400+02 526.8 2.170-03 9.9100+02 526.8 2.180-03 9.9800+02 526.8 4.600-03 3.3750+03 526.8 6.900-03 6.8700+03 526.8 8.600-03 1.0245+04 526.8 1.010-02 1.3741 +04 526.8 1.260-02 2.0370+04 526.8 1.510-02 2.7481 +04 526.8 1.760-02 3.4834+04 526.8 2.010-02 4.1945+04 526.8 2.260-02 4.8936+04 526.8 2.363-02 5.1640+04 526.8 2.771-02 5.1640+04 526.8 2.772-02 2.7786+04 526.8 3.010-02 3.0200+04 526.8 3.260-02 3.2523 +04 526.8 3.510*02 3.4576+04 526.8 3.760-02 3.6359+04 526.8 4.010-02 3.7764+04 526.8 4.260-02 3.8898 +04 526.8 4.780-02 4.0141 +04 526.8 1.000+00 4.0141 +04 526.8 Rev. 49, 04/96

AutoCAD: Figure Fsar 6A_1A.dwg FSAR REV.65 FIGURE 6A-1A, Rev. 55 REACTOR SHIELD ANNULUS ARRANGEMENT SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

Security-Related Information Figure Withheld Under 10 CFR 2.390 FIGURE 6A-1B RPV SHIELD WALL AND PEDESTAL SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_2.dwg FSAR REV.65 FIGURE 6A-2, Rev. 47 RPV SHIELD ANNULUS SUBCOMPARTMENT MODEL SCHEMATIC SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3A.dwg FSAR REV.65 FIGURE 6A-3A, Rev. 47 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A RECIRC. LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3B.dwg FSAR REV.65 FIGURE 6A-3B, Rev. 47 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A RECIRC.

LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3C.dwg FSAR REV.65 FIGURE 6A-3C, Rev. 47 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A RECIRC.

LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3D.dwg FSAR REV.65 FIGURE 6A-3D, Rev. 47 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A RECIRC.

LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3E.dwg FSAR REV.65 FIGURE 6A-3E, Rev. 47 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A RECIRC.

LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3F.dwg FSAR REV.65 FIGURE 6A-3F, Rev. 47 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A RECIRC.

LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3G.dwg FSAR REV.65 FIGURE 6A-3G, Rev. 48 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A FEEDWATER LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3H.dwg FSAR REV.65 FIGURE 6A-3H, Rev. 48 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A FEEDWATER LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3I.dwg FSAR REV.65 FIGURE 6A-3I, Rev. 48 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A FEEDWATER LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3J.dwg FSAR REV.65 FIGURE 6A-3J, Rev. 48 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A FEEDWATER LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3K.dwg FSAR REV.65 FIGURE 6A-3K, Rev. 48 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A FEEDWATER LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_3L.dwg FSAR REV.65 FIGURE 6A-3L, Rev. 48 PRESSURE TRANSIENT IN SHIELD ANNULUS FOLLOWING A FEEDWATER LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_4.dwg FSAR REV.65 FIGURE 6A-4, Rev. 47 DRYWELL HEAD ARRANGEMENT SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_5.dwg FSAR REV.65 FIGURE 6A-5, Rev. 47 HEAD SPRAY LINE BREAK GEOMETRY SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_6.dwg FSAR REV.65 FIGURE 6A-6, Rev. 47 PRESSURE RESPONSE IN THE DRYWELL HEAD FOR A HEAD SPRAY LINE BREAK SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_7.dwg FSAR REV.65 FIGURE 6A-7, Rev. 47 FORCE TRANSIENT ON REACTOR PRESSURE VESSEL FOLLOWING A RECIRC. LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_8.dwg FSAR REV.65 FIGURE 6A-8, Rev. 47 FORCED TRANSIENT ON REACTOR SHIELD WALL FOLLOWING RECIRC.

LINE BREAK AT THE NOZZLE SAFE END SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_9.dwg FSAR REV.65 FIGURE 6A-9, Rev. 48 RESULTANT FORCE TRANSIENT ON RPV FOLLOWING A FEEDWATER LINE BREAK AT THE NOZZLE SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

AutoCAD: Figure Fsar 6A_10.dwg FSAR REV.65 FIGURE 6A-10, Rev. 48 RESULTANT FORCE ON SHIELD WALL FOLLOWING A FEEDWATER LINE BREAK AT THE NOZZLE SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT

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