ML17061A124

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B/B - UFSAR Attachment C3.6 Main Steamline Break in Main Steam Tunnel
ML17061A124
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 02/08/2017
From:
Exelon Generation Co
To:
NRC/EDO
References
Download: ML17061A124 (43)
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B/B-UFSAR ATTACHMENT C3.6 MAIN STEAMLINE BREAK IN MAIN STEAM TUNNEL

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B/B-UFSAR TABLE OF CONTENTS PAGE I. Introduction C3.6-1 II. Analysis C3.6-2 A. Description of the Computer Code C3.6-2 B. Simulation of the System C3.6-2

1. Assumptions C3.6-2
2. Analytical Model C3.6-3 III. Results and Conclusions C3.6-3 A. Unit 1 Results C3.6-3
1. Pipe Break in the Main Steam Tunnel C3.6-3
2. Pipe Break in Valve Room C3.6-4 B. Unit 1 Conclusions C3.6-4 C. Unit 2 Results C3.6-4
1. Pipe Break in the Main Steam Tunnel C3.6-4
2. Pipe Break in Valve Room C3.6-4 D. Unit 2 Conclusions C3.6-5 IV. References C3.6-5 C3.6-i REVISION 7 - DECEMBER 1998

B/B-UFSAR LIST OF TABLES NUMBER TITLE PAGE 1 Unit 1 Subcompartment Nodal Description C3.6-6 2 Unit 2 Subcompartment Nodal Description C3.6-9 3 Subcompartment Vent Flow Path Description C3.6-12 4 Unit 1 Blowdown Rates and Enthalpy for Main Steamline Break C3.6-17 5 Unit 2 Blowdown Rates and Enthalpy for Main Steamline Break C3.6-20 6 Summary of Unit 1 Peak Pressures Between Valve Rooms and Main Steam Tunnel C3.6-21

)

C3.6-ii REVISION 7 - DECEMBER 1998

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B/B-UFSAR LIST OF FIGURES NUMBER TITLE C3.6-1 Main Steam Tunnel View Plan C3.6-2 Nodalization Schematic C3.6-3 Unit 1-Differential Pressure vs. Time, Main Steam Line Break in Lower Second Quadrant Valve Room (Node

5) (Volumes 2, 3, 4, and 5)

C3.6-4 Unit 1-Differential Pressure vs. Time, Main Steam Line Break in Second Quadrant Tunnel (Node 6) and Main Steam.Line Break in Second and First Quadrant Tunnel (Node 7)

C3.6-5 Unit 1-Differential Pressure vs. Time, Main Steam Line Break in First Quadrant Tunnel (Node 8) and Main Steam Line Break in First Quadrant Tunnel (Node 13)

C3.6-6 Unit 1-Differential Pressure vs. Time, Main Steam Line Break in First Quadrant Tunnel (Node 14)

C3.6-7 Unit 2 Differential Pressure vs. Time for Nodes 2, 3, 4, and 5 (Break in Node 5)

C3.6-8 Unit 2 Differential Pressure vs. Time for Nodes 6, 7, 8, 13, and 14 (Break in Node 5)

C3.6-9 Unit 2 Differential Pressure vs. Time for Nodes 9, 10, 11, and 12 (Break in Node 5)

C3.6-10 Unit 2 Differential Pressure vs. Time for Nodes 2, 3, 4, and 5 (Break in Node 6)

C3.6-ll Unit 2 Differential Pressure vs. Time for Nodes 6, 7, 8, 13, and 14 (Break in Node 6)

C3.6-12 Unit 2 Differential Pressure vs. Time for Nodes 9, 10, 11, and 12 (Break in Node 6)

C3.6-13 Unit 2 Differential Pressure vs. Time for Nodes 2, 3, 4, and 5 (Break in Node 7)

C3.6-14 Unit 2 Differential Pressure vs. Time for Nodes 6, 7, 8, 13, and 14 (Break in Node 7)

C3.6-15 Unit 2 Differential Pressure vs. Time for Nodes 9, 10, 11, and 12 (Break in Node 7)

C3.6-16 Unit 2 Differential Pressure vs. Time for Nodes 2, 3, 4, and 5 (Break in Node 8)

C3.6-17 Unit 2 Differential Pressure vs. Time for Nodes 6, 7, 8, 13, and 14 (Break in Node 8)

C3.6-18 Unit 2 Differential Pressure vs. Time for Nodes 9, 10, 11, and 12 (Break in Node 8)

C3.6-iii REVISION 7 - DECEMBER 1998

B/B-UFSAR ATTACHMENT C3.6 - MAIN STEAMLINE BREAK IN MAIN STEAM TUNNEL I. Introduction One of the design criteria for the main steam tunnel and valve room subcompartments is to retain functional integrity indefinitely, that is, to have the capability of withstanding peak transient differential pressures under a postulated accident mode.

It was the purpose of this study to determine the transient pressure response in the Unit 1 and Unit 2 main steam tunnels and the associated safety valve rooms in the first and second quadrants at the time of a sudden and complete circumferential failure of a main steamline.

Six break locations for Unit 1 and four for Unit 2 were considered. The common locations are the lower valve room just downstream of the isolation valve; the main steam tunnel just outside the valve room in the first quadrant; the main steam tunnel between the first and second quadrants; and the main steam tunnel just outside the valve room in the second quadrant. Additionally, Unit 1 was evaluated for two breaks in the first quadrant between the valve room and the turbine building opening.

Qualification tests have been conducted for the components in the safety valve house. The components include the main steam and main feedwater isolation valves, the main steam power-operated relief valve, and the main steam safety valves. These tests conservatively applied aging, radiation, seismic, and worst case environmental (temperature, pressure, and humidity) loading to the components, and showed that loss of function did not occur.

The portion of the main steam and main feedwater pipe in the tunnel between the safety valve house and the turbine building meets the guidelines of Branch Technical Position APSCB3-1. A special pipe whip restraint is located around each pipe as it passes through the wall separating the isolation valve room from the main steam tunnel. This restraint limits the amount of strain that can be transmitted to the isolation valves from any pipe break in the tunnel to a level which will not interfere with the proper functioning of the isolation valves.

The safety valve house, the steam tunnel, and the compartment between the containment and the safety valve house all have the same basis for design. These compartments have been designed for pressurization, impingement, and temperature as specified in Table 3.8-10, load combinations 8, 13, and 14.

C3.6-1 REVISION 7 - DECEMBER 1998

B/B-UFSAR An assumed pipe crack or break in the tunnel, isolation valve room , or safety valve house cannot cause structural failure.

The subcompartment pressurization analysis is included in this attachment. The methods used to calculate the pressure buildup in subcompartments outside the containment are the same as those used for subcompartments inside the containment.

II. Analysis A. Description of the Computer Code The analysis was carried out by using the RELAP code, which is a multicell thermal-hydraulic transient analysis computer program.

The basis for the computer code is a network of fluid control volumes (fluid nodes) and fluid paths (interconnecting control volumes) for which the conservation equations of mass, momentum, and energy are solved in space and time. Superimposed on the network are computer subroutines which permit physical modeling of the reactor system, the containment, plant subcompartments, safeguard fluid systems and the pipe break flow.

B. Simulation of the System

1. Assumptions The following are the major assumptions used in this study:
a. The initial conditions in the steam tunnel and the valve rooms are 14.7 psia of pressure at a temperature of 90°F and a relative humidity of 30%.
b. Only one break occurred per analysis.
c. The Moody choked-flow calculation was used with a multiplier of 0.6 as required by the NRC for choked-flow check between nodes.
d. Homogeneous fine mist for the steam/water-air system in the control volumes with complete liquid carryover was used to produce a conservative solution.
e. The length of a flow path connecting any two control volumes was taken as the distance between the centroids of these volumes.
f. The area of a flow path is the effective area (i.e.,

the cross-sectional area of the path excluding areas occupied by grating, pipes, louvers, etc.).

C3.6-2 REVISION 7 - DECEMBER 1998

B/B-UFSAR

g. Mass and energy release rate for a postulated main steamline break is included in Tables 4 and 5 for Unit 1 and Unit 2 respectively.
h. The doors and HVAC louvers/panels in the upper chambers of the valve rooms are initially assumed closed or intact. A differential pressure equal to 1.5 psi will blow open the doors and panels .to atmosphere.
2. Analytical Model To determine the transient pressures and temperatures in the main steam tunnel and the safety valve rooms after a sudden failure of a main steamline, the main steam tunnel was simulated by five control volumes connected by flow paths. The area of each flow path is equivalent to the net area of the steam tunnel.

The subcompartments of the valve room in each quadrant were represented by four control volumes connected by flow paths. The area of each flow path was equivalent to the total vent areas between subcompartments.

Figures 1 and 2 depict a plan of the, system and the flow diagram of the analytical model used in the study, respectively.

Tables 1, 2 and 3 give the dimensions of the control volumes and flow paths, while Tables 4 and 5 show the blowdown rates and properties versus time from a postulated main steamline break as provided by Framatome Technologies International for Unit 1 '

(Reference 2) and Westinghouse for Unit 2, respectively.

III. Results and Conclusions A. Unit 1 Results The peak nodal differential pressures, which represent the difference between steam tunnel/valve room nodes and the surrounding areas, are presented in Table 1 and Figures C3.6-3 through C3.6-6.

The peak differential pressures across internal walls and floors are shown in Table 6 and Figures C3.6-7 and C3.6-8.

1. Pipe Break in the Main Steam Tunnel Five locations of a postulated main steamline break were considered in the main steam tunnel. The first and second locations were just outside the valve rooms in the first and second quadrants (Nodes 6 and 8), respectively. The third C3.6-3 REVISION 7 - DECEMBER 1998

B/B-UFSAR location was in the steam tunnel between the first and second quadrants (Node 7) . The last two break locations are in the tunnel leading to the entrance to the turbine building (Nodes 13 and 14) .

Figures C3.6-4 through C3.6-6 show the differential pressures in the control volumes directly affected by the line breaks in the tunnel. J

2. Pipe Break in Valve Room A pipe break in the lower chamber of the valve room in the second quadrant (Node 5) was evaluated to provide the most conservative differential pressure.

Figure C3.6-3 shows the differential pressures in the control volumes directly affected by the line break in the valve room.

Tables 1 and 6 provide a summary of the peak pressures used in the qualification of the structure (References 3 and 4).

B. Unit 1 Conclusions The integrity of the Unit 1 main steam tunnel and valve rooms in both the first and second quadrants can be maintained during a postulated main steamline break. These differential pressures, modified by dynamic load factors, were used to qualify the subject walls fo~ the tunnels (Reference 3) and valve rooms (Reference 4).

C. Unit 2 Results

1. Pipe Break in the Main Steam Tunnel Three locations of a postulated main steamline break were considered in the main steam tunnel. The first and second locations were just outside the valve rooms in the first and second quadrants (Nodes 6 and 8), respectively. The third location was in the steam tunnel between the first and second quadrants (Node 7) .

Figures 10 through 18 show the differential pressures in the control volumes directly affected by the line break.

2. Pipe Break in Valve Room A pipe break in the lower chamber of the valve room in the second quadrant (Node 5) was considered to give the most conservative differential pressure.

Figures 7 through 9 show the differential pressures in the affected control volumes after a line break.

I C3.6-4 REVISION 7 - DECEMBER 1998

B/B-UFSAR Table 2 gives a summary of the peak pressures to the valves used in the design of the structure.

D. Unit 2 Conclusions The integrity of the main steam tunnel, the auxiliary feedwater tunnel, and the valve rooms in both the first and second quadrants can be maintained during a postulated main steamline break.

IV. References(

1. Calculation 3C8-0282-001, Revision 3.
2. NDIT 960136, "Steam Generator Replacement Project:

Transmittal of Steam Line Break Mass and Energy for Steam Tunnel Pressure Analysis," dated September 16, 1996.

3. Calculation 5.6.l-BYR96-233/5.6.l-BRW-96-604, Revision 0.
4. Calculation 5.6.3-BYR96-234/5.6.3-BRW-96-608, Revision 0.

C3.6-5 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 1 UNIT 1 SUBCOMPARTMENT NODAL DESCRIPTION MAIN STEAM LINE BREAK IN UNIT 1 MAIN STEAM TUNNEL OR VALVE ROOMS DBA BREAK CONDITIONS CALC. DESIGN CROSS- BREAK PEAK PEAK SECTIONAL INITIAL CONDITIONS LOC. BREAK PRESS PRESS DESIGN VOLUME HEIGHT AREA VOLUME TEMP. PRESS. HUMID.* VOL. BREAK AREA BREAK DIFF. DIFF. MARGIN NO. DESCRIPTION ft ft 2 ft 3 Op psi a  %- NO. LINE ft' TYPE psid psid  %-

1 Atmosphere 5x10 3 lx10 3 107 90 14.7 30 2 2nd Quad- 12.33 133.25 4895.7 90 14.7 30 5 Main 1.4 Double- 15.3 26.2 71 rant Upper Steam ended Valve Guillo-Chamber tine 3 2nd Quad- 12.33 183.7 4895.7 90 14.7 30 5 Main 1. 4 Double- 15.3 26.2 71 rant Upper Steam ended Valve Guillo-Chamber tine 4 2nd Quad- 24.00 213. 0 6007.0 90 14.7 30 5 Main 1.4 Double- 17.7 26.2 48 rant Lower Steam ended Valve Guillo-Chamber tine 5 2nd Quad- 24.00 213.0 6007.0 90 14.7 30 5 Main 1. 4 Double- 17.7 28.6 62 rant Valve Steam ended Chamber Guillo-tine

  • Relative humidity.

C3.6-6 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 1 (Cont'd)

DBA BREAK CONDITIONS CALC. DESIGN CROSS- BREAK PEAK PEAK SECTIONAL INITIAL CONDITIONS LOC. BREAK PRESS PRESS DESIGN VOLUME HEIGHT AREA VOLUME TEMP. PRESS. HUMID.* VOL. BREAK AREA BREAK DIFF. DIFF. MARGIN NO. DESCRIPTION ft ft 2 ft 3 OF psia 'o NO. LINE ft 2 TYPE psid psid 'o 6 2nd Quad- 19.00 317.0 13695.0 90 14.7 30 6 Main 1.4 Double- 16.0 26.5 66 rant Main Steam ended Steam Guillo-Tunnel tine 7 Main Steam 19.00 203.00 34865.0 90 14.7 30 7 Main 1.4 Double- 15.2 21. 3 40 Tunnel Steam ended Guillo-tine 8 1st Quad- 20.00 432.0 35016.0 90 14.7 30 8 Main 1.4 Double- 8.3 11.2 35 drant Steam Steam ended Tunnel Guillo-tine 9 1st Quad- 12.33 133.25 4895.7 90 14.7 30 5** Main 1.4 Double- 15.3 26.2 71 rant Upper Steam ended Valve Guillo-Chamber tine 10 1st Quad- 12.33 183.7 4895.7 90 14.7 30 5** Main 1. 4 Double- 15.3 26.2 71 rant Upper Steam ended Valve Guillo-Chamber tine

  • Relative humidity.
    • Differential pressures calculated for 1st quadrant valve chambers are also applicable to corresponding 2nd quadrant valve chambers.

C3.6-7 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE_1 (Cont'd)

DBA BREAK CONDITIONS CALC. DESIGN CROSS- BREAK PEAK PEAK SECTIONAL INITIAL CONDITIONS LOC. BREAK PRESS PRESS DESIGN VOLUME HEIGHT AREA VOLUME TEMP. PRESS. HUMID.* VOL. BREAK AREA BREAK DIFF. DIFF. MARGIN NO. DESCRIPTION ft ft 2 ft 3 OF psia  % NO. LINE ft 2 TYPE psid psid  %

11 1st Quad- 24.00 213.0 6007.0 90 14.7 30 5** Main 1. 4 Double- 17.7 28.6 62 rant Valve Steam ended Chamber Guillo-tine 12 1st Quadrant 24.00 213.0 6007.0 90 14.7 30 5** Main 1.4 Double- 17.7 28.6 62 Lower Valve Steam ended Chamber Guillo-tine 13 1st Quad- 29.00 432.0 17388.4 90 14.7 30 13 Main 1.4 Double- 10.7 13.2 23 rant Main Steam ended Steam Guillo-Tunnel tine 14 1st Quad- 19.00 280.0 13529.9 90 14.7 30 14 Main 1.4 Double- 11. 3 *** **.:!'

rant Main Steam ended Steam Guillo-Tunnel tine

  • Relative humidity.
    • Differential pressures calculated for 1st quadrant valve chambers are also applicable to corresponding 2nd quadrant valve chambers.
      • The calculated peak differential pressure in Node 14 has been evaluated to be within plant design basis code allowable stresses (Reference 3) .

C3.6-8 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 2 UNIT 2 SUBCOMPARTMENT NODAL DESCRIPTION MAIN STEAM LINE BREAK IN UNIT 2 MAIN STEAM TUNNEL OR VALVE ROOMS DBA BREAK CONDITIONS CALC. DESIGN CROSS- BREAK PEAK PEAK SECTIONAL INITIAL CONDITIONS LOC. BREAK PRESS PRESS DESIGN VOLUME HEIGHT AREA VOLUME TEMP. PRESS. HUMID.* VOL. BREAK AREA BREAK DIFF. DIFF. MARGIN NO. DESCRIPTION ft ft2 ft' op psia  % NO. LINE ft 2 TYPE psid psid  %

3 3 7 1 Atmosphere 5xl0 lxl0 10 90 14. 7 30 2 2nd Quad- 12.33 133. 2~ 4895.7 90 14.7 30 5 Main 1.4 Double- 17.4 26.2 51 rant Upper Steam ended Valve Guillo-Chamber tine 3 2nd Quad- 12.33 183.7 4895.7 90 14.7 30 5 Main 1.4 Double- 17.4 26.2 51 rant Upper Steam ended Valve Guillo-Chamber tine 4 2nd Quad- 24.00 213. 0 6007.0 90 14.7 30 5 Main 1.4 Double- 17.4 26.2 51 rant Lower Steam ended Valve Guillo-Chamber tine 5 2nd Quad- 24.00 213. 0 6007.0 90 14.7 30 5 Main 1. 4 Double- 19.7 28.6 45 rant Valve Steam ended Chamber Guillo-tine

  • Relative humidity.

C3.6-9 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 2 (Cont'd)

DBA BREAK CONDITIONS CALC. DESIGN CROSS- BREAK PEAK PEAK SECTIONAL INITIAL CONDITIONS LOC. BREAK PRESS PRESS DESIGN VOLUME HEIGHT AREA VOLUME TEMP. PRESS. HUMID.* VOL. BREAK AREA BREAK DIFF. DIFF. MARGIN NO. DESCRIPTION ft ft' ft 3 OF psi a  % NO. LINE ft 2 TYPE psid psid  %

6 2nd Quad- 19.00 317.0 13695.0 90 14.7 30 6 Main 1.4 Double- 16.4 26.5 61 rant Main Steam ended Steam Guillo-Tunnel tine '\

7 Main Steam 19.00 203.00 34865.0 90 14.7 30 7 Main 1.4 Double- 15.5 21. 3 38 Tunnel Steam ended Guillo-tine 8 1st Quad- 20.00 432.0 35016.0 90 14.7 30 8 Main 1.4 Double- 8.8 11.2 28 drant Steam Steam ended '

Tunnel Guillo-tine 9 1st Quad- 12.33 133. 25 4895.7 90 14.7 30 5** Main 1.4 Double- 17.4 26.2 51 rant Upper Steam ended Valve Guillo-Chamber tine 10 1st Quad- 12.33 183.7 4895.7 90 14.7 30 5** Main 1.4 Double- 17.4 26.2 51 rant Upper Steam ended Valve Guillo-Chamber tine

  • Relative humidity.
    • Differential pressures calculated for 1st quadrant valve chambers are also applicable to corresponding 2nd quadrant valve chambers.

C3.6-10 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 2 (Cont'd)

DBA BREAK CONDITIONS CALC. DESIGN CROSS- BREAK PEAK PEAK SECTIONAL INITIAL CONDITIONS LOC. BREAK PRESS PRESS DESIGN VOLUME HEIGHT AREA VOLUME TEMP. PRESS. HUMID.* VOL. BREAK AREA BREAK DIFF. DIFF. MARGIN NO. -DESCRIPTION ft ft2 ft 3 OF psi a  %- NO. LINE ft2 TYPE psid psid  %-

11 1st Quad- 24.00 213. 0 6007.0 90 14.7 30 5** Main 1. 4 Double- 19.7 28.6 45 rant Valve Steam ended Chamber Guillo-tine 12 1st Quadrant 24.00 213. 0 6007.0 90 14.7 30 5** Main 1.4 Double- 19.7 28.6 45 Lower Valve Steam ended Chamber Guillo-tine 13 1st Quad- 29.00 432.0 17388.4 90 14.7 30 8 Main 1.4 Double- 8.9 13.2 48 rant Main Steam ended Steam Guillo-Tunnel tine 14 1st Ql.Jad- 19.00 280.0 13529.9 90 14.7 30 8 Main 1. 4 Double- 5.9 10.3 75 rant Main Steam ended Steam Guillo-Tunnel tine

  • Relative humidity.
    • Differential pressures calculated for 1st quadrant valve chambers are also applicable to corresponding 2nd quadrant valve chambers.

C3.6-11 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 3 SUBCOMPARTMENT VENT PATH DESCRIPTION MAIN STEAM LINE BREAK IN MAIN STEAM TUNNEL OR VALVE ROOM FROM TO DESCRIPTION VENT VOL. VOL. OF HYDRAULIC HEAD LOSS, K PATH NODE NODE VENT PATH FLOW* AREAt LENGTH 1 DIAMETER FRICTION TURNING EXPAN- CONTRAC-NO. NO. NO. CHOKED'! UN CHOKED ft2 ft ft K, ft/d LOSS, K SION, K TION, K TOTAL 1 14 1 Main Steam Tunnel to Turbine 270.8 28.0 13. 9 1.0656 Building Unchoked 2 2 5 2nd Quadrant Upper Valve Chamber 121.0 16.4 5.7 1.5207 to Lower Valve Chamber Unchoked 3 3 4 2nd Quadrant Upper Valve Chamber 121.0 16.4 5.7 1.5207 to Lower Valve Chamber Unchoked 4 6 4 2nd Quadrant Lower Valve Chamber 73.0 17.2 4.5 1.5685 to Main Steam Tunnel Unchoked 5 6 5 2nd Quadrant Lower Valve Chamber 73.0 17.2 4.5 1.5685 to Main Steam Tunnel Choked (5)

  • See Figures 1 and 2.

Length/area is the inertial term input directly into RELAP4/MODS.

Number in parentheses indicates the volume number of the break location which caused choke flow in the vent.

For break locations not indicated, unchoked flow had occurred for the vent.

C3.6-12 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 3 (Cont'd)

FROM TO DESCRIPTION VENT VOL. VOL. OF HYDRAULIC HEAD LOSS, K PATH NODE NODE VENT PATH FLOW* AREAt LENGTH' DIAMETER FRICTION TURNING EXPAN- CONTRAC-NO. NO. NO. CHOKEDf UNCHOKED ft 2 ft ft K, ft/d LOSS, K SION, K TION, K TOTAL 6 5 4 Openings Between 2nd Quadrant 100.0 16.1 7.1 1. 5071 Lower Valve Chambers Un choked 7 6 7 2nd Quadrant Main Steam Tunnel 199.8 102.0 13.3 2.1860 to Main Steam Tunnel Unchoked 8 7 8 Main Steam Tunnel to 1st Quadrant 199.8 132 .4 13.3 2.7530 Main Steam Tunnel Unchoked 9 12 9 1st Quadrant Upper Valve Chamber 121. 0 16.4 5.7 1. 5207 to Lower Valve Chamber Unchoked 10 9 10 Openings Between 1st Quadrant 100.0 11.2 4.5 1.5120 Upper Valve Chambers Unchoked 11 11 10 1st Quadrant Upper Valve Chamber 121.0 16.4 5.7 1. 5207 to Lower Valve Chamber Unchoked

  • See Figures l and 2.

Length/area is the inertial term input directly into RELAP4/MOD5.

Number in parentheses indicates the volume number of the break location which caused choke flow in the vent.

For break locations not indicated, unchoked flow had occurred for the vent.

C3.6-13 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 3 (Cont'd)

FROM TO DESCRIPTION ')

VENT VOL. VOL. OF HYDRAULIC HEAD LOSS, K PATH NODE NODE VENT PATH FLOW* AREAt LENGTH' DIAMETER FRICTION TURNING EXPAN- CONTRAC-NO. NO. NO. CHOKED~ UN CHOKED ft2 ft ft K, ft/d LOSS, K SION, K TION, K TOTAL 12 12 11 Openings Between 1st Quadrant 100.0 16.1 7.1 1. 5071 Lower Valve Chambers Unchoked 13 .8 13 1st Quadrant Main Steam Tunnel 373.6 42.0 17.6 2.2600 Unchoked 14 13 14 1st Quadrant Main Steam Tunnel 270 .. 8 42.0 13.9 2.2600 Unchoked 15 8 11 1st Quadrant Lower Valve Chamber 73.0 17.2 4.5 1. 5685 to Main Steam Tunnel Unchoked 16 8 12 1st Quadrant Lower Valve Chamber 73.0 17.2 4.5 1.5685 to Main Steam Tunnel Unchoked 17 2 3 Openings Between 2nd Quadrant 100.0 11. 2 4.5 1.5120 Upper Valve Chambers Unchoked

  • See Figures 1 and 2.

Length/area is the inertial term input directly into RELAP4/MOD5.

Number in parentheses indicates the volume number of the break location which caused choke flow in the vent.

For break locations not indicated, unchoked flow had occurred for the vent.

C3.6-14 REVISION 7 DECEMBER 1998

B/B-UFSAR TABLE 3 (Cont'd)

FROM TO DESCRIPTION VENT VOL. VOL. OF HYDRAULIC HEAD LOSS, K PATH NODE NODE VENT PATH FLOW* AREAt LENGTH' DIAMETER FRICTION TURNING EXPAN- CONTRAC-NO. NO. NO. CHOKEDt UNCHOKED ft2 ft ft K, ft/d LOSS, K SION, K TION, K TOTAL 18 2 1 HVAC Panels in 2nd Quadrant 51. 3 15.2 5.9 2.900 Upper Valve Chambers Choked (5' 6) 19 3 1 Door and HVAC Panels in 2nd 75.8 25.3 5.4 2.900 Quadrant Upper Valve Chambers Choked (5, 6) 20 9 1 HVAC Panels in 1st Quadrant Upper Valve Chamber 51. 3 15.2 5.9 2.900 Choked (5) § 21 10 1 Door and HVAC Panels in 1st 75.8 25.3 5.4 2.900 Quadrant Upper Valve Chamber Choked (5) 4 22(a) 0 5 Main Steam Line Break in Node 5 1. 0 0.0 0.0 0.000 Fill 5

22 (b) 0 6 Main Steam Line Break in Node 6 1. 0 0.0 0.0 0.000 Fill

  • See Figures 1 and 2.

Length/area is the inertial term input directly into RELAP4/MOD5.

Number in parentheses indicates the volume number of the break location which caused choke flow in the vent.

For break locations not indicated, unchoked flow had occurred for the vent.

§ Choking.results for 2nd quadrant valve room are applied to 1st quadrant valve room.

    • Four cases were considered each having a different break location.

C3.6-15 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 3 (Cont'd)

FROM TO DESCRIPTION VENT VOL. VOL. OF HYDRAULIC HEAD LOSS, K PATH NODE NODE VENT PATH FLOW* AREAt LENGTH' DIAMETER FRICTION TURNING EXPAN- CONTRAC-NO. NO. NO. CHOKEDt UNCHOKED ft' ft ft K, ft/d LOSS, K SION, K TION, K TOTAL 22(c) 0 7 Main Steam Line Break in Node 7 1. 0 0.0 0.0 0.000 Fill 5

22 (d) 0 8 Main Steam Line Break in Node 8 1. 0 0.0 0.0 0.000 Fill

  • See Figures 1 and 2.

Length/area is the inertial term input directly into RELAP4/MOD5.

Number in parentheses indicates the volume number of the break location which caused choke flow in the vent.

For break locations not indicated, unchoked flow had occurred for the vent.

§ Choking results for 2nd quadrant valve room are applied to 1st quadrant valve room.

    • Four cases were considered each having a different break location.

C3.6-16 REVISION 7 DECEMBER 1998

B/B-UFSAR TABLE 4 UNIT 1 BLOWDOWN RATES AND ENTHAL~Y FOR MAIN STEAMLINE BREAK TIME FLOW ENTHALPY (sec) (lb/sec) (Btu/lb) 0.0 14,189 1,024.9 0.02 14,189 1,024.9 0.04 13,883 1,116.4 0.06 12,901 1,119.3 0.08 12,479 1,124.6 0.10 12,342 1,133.0 0.12 12,250 1,134.0 0.14 12,093 1,128.3 0.16 11,827 1,119.4 0.18 11,434 1,111.2 0.20 11,022 1,107.3 0.22 10,642 1,105.7 0.24 10,315 1,105.5 0.26 10,041 1,105.9 0.28 9,810 1,106.3

0. 3 0 9,608 1,106.4 0.32 9,424 1,106.4 0.34 9,255 1,106.3 0.36 9,097 1,106.4 0.38 8,954 1,106.8 0 .40 8,827 1,107.7 0.42 8,728 1,110.1 0.44 8,633 1,109.1 C3.6-17 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 4 (Cont'd)

TIME FLOW ENTHALPY (sec) (lb/sec) (Btu/lb) 0.46 8,558 1,112.7 0.48 8,522 1,116.4 0.50 8,512 1,119.5 0.52 8,523 1,122.7 0.54 8,553 1,125.9 0.56 8,598 1,128.8 0.58 8,652 1,131.3 0.60 8,709 1,133.3 0.62 8,765 1,134.8 0.64 8,813 1,135.8 0.66 8,852 1,136.5 0.68 8,879 1,136.9 0.70 8,894 1,137.2 0.72 8,898 1,137.3 0.74 8,892 1,137.4 0.76 8,878 1,137.5 0.78 8,875 1,138.5 0.80 8,846 1,137.5 0.82 8,816 1,137.9 0.84 8,788 1,138.3 0.86 8,761 1,138.5 0.88 8,733 1,138.7 0.90 8,705 1.138.9 0.92 8,679 1,139.1 C3.6-18 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 4 (Cont'd)

TIME FLOW ENTHALPY (sec) (lb/sec) (Btu/lb) 0.94 8,655 1,139.3 0.96 8,632 1,139.5 0.98 8,611 1,139.6

1. 00 8,591 1,139.8
1. 02 8,573 1,139.9
1. 04 8,557 1,140.1
1. 06 8,542 1,140.2
1. 08 8,529 1,140.3 1.10 8,518 1,140.4 1.12 8,508 1,140.5 1.14 8,499 1,140.5 1.16 8,492 1,140.5 1.18 8,486 1,140.4
1. 20 8,481 1,140.3
1. 22 8,477 1,140.2 1.24 8,473 1,140.0
1. 26 8,471 1,139.7 1.28 8,468 1,139.4
1. 30 8,466 1,139.0 1.32 8,465 1,138.6 1.34 8,463 1,138.1
1. 36 8,462 1,137.5 1.38 8,462 1,136.9 1.40 8,461 1.136.2 C3.6-19 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 5 UNIT 2 BLOWDOWN RATES AND ENTHALPY FOR MAIN STEAMLINE BREAK TIME FLOW ENTHALPY (sec) (lb/sec) (Btu/lb) 0.0 11,000 1,195.4 2.0 10,434 1,195.1 4.0 9,608 1,196.9 6.0 9,017 1,197.7 8.0 8,613 1,199.4 10.0 9,318 1,199.8 10.1 2,098 1,201.1 20.0 1,993 1,199.2 30.0 1,879 1,208.1 50.0 1,625 1,206.1 75.0 1,064 1,203.0 100.0 814 1,201.5 C3.6-20 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 6

SUMMARY

OF UNIT 1 PEAK PRESSURES BETWEEN VALVE ROOM AND MAIN STEAM TUNNEL PEAK WALL LOCATION DELTA P PRESSURE BETWEEN NODES ACROSS (psid) 2-3 9-10 Vertical Wall 5.48 3-4 10-11 Horizontal Floor 12.50 4-5 11-12 Vertical Wall 13.20 2-5 9-12 Horizontal Floor 12.50 4-6 5-6 Main Steam Tunnel 11-8 12-8 Vertical Wall 14.40 C3.6-21 REVISION 7 - DECEMBER 1998

Safety Valve Room __,

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Section View B-B BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE C3.6*1 MAIN STEAM TUNNEL VIEW PLAN

REVISION 7 DECEMBER 1998 D- NOl>E

~ = JUNCTION l

~ BR&AX 2 3 LOCA'.t'IONS 6

10 ll NOTE: A DESCRIPTION OF EACH OF THE NODES IS GIVEN IN TABLES 1 AND 2.

BYRON/BRAIDWOOD ST.!:..TIONS UPDATED i='INAL SAFETY ANALYSIS REPORT FIGURE C3.6-2 NODAL!ZATION SCHEMATIC 229

REVISION 7 DECEMBER 1998 MA:1N STEAMiLINE BREAK 1N LOWER 1ND QUADRANT VALVE ROOM (NODE!)

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AND VOLUMES 4 ANO 5 (BREAK IN NODE 5) 230

REVISION 7 DECEMBER 1998 MAIN S'IEil! LINE BJlEAK DI 2M1>>

QUADRANTTDNNEL (NODE 6)

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BYRON/BRAIDWOOD STATIONS UPDATED ~INAL SAFETY ANALYSIS REPORT FIGURE C3.5-4 UNiT 1 DIFFERENTIAL PRESSURE VS. T!ME FOR VOLUME 6 (BREAK IN NODE 6)

AND VOLUME 7 (BREAK iN NODE 7) 231

REVISION 7

~ .../

DECEMBER 1998 MAIN STEAM I.DIE BREAK Df lST QUADRANT 01 TDNMEL (NODE I) 10.0 l-vo1wne Ii

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BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSiS REPORT FIGURE C3.6-5 UNIT 1 DIFFERENTIAL PRESSURE VS. TIME FOR VOLUME 8 (BREAK IN NOOE 8)

AND VOLUME 13 (BR~AK IN NOOE 13) 232

7 REVISION 7 DECEMBER 1998 Maia Steam Uae Break ID 1st Qaadraat of Miia Stam TwlDd (Node i4)

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BYRON/BRAIDWOOD STATIONS UPDATED F! NAL SAFETY ANALYSIS REPORT FIGURE C3.6-6 UNIT 1

  • DIFFERENTiAL PRESSURE VS. TIME FOR VOLUME i 4 (BR~AK IN NOOE 14) 233

REVISION 7 DECEMBER 1998 c

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REVISION 7 DECEMBER 1998 "RfNITEAft LlNE BREAK IN L8Y£1t ZHU flUADQ VALVE Kean lNIDE S)

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REVISION 7 DECEMBER 1998 10.0...-~--~~==-=~--~--~~----..-.--~~~~~~==-...

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REVISION 7 DECEMBER 1998 ftRJNSTER" LINE DRERK IN 2HD QUAD TUNNEL fNBDE OJ ilr1E UJttJ ftAINSTEArt LJNE MERK JN 2Nf1 OUM TUNNEL CNl!DE fU TlHE tSECJ BYRON/BRAIDWOOD STATiONS UPDATED FiNAL SAF::TY ANALYSIS ~EPORT FIGUR~ C3. 6-10 UN!T 2 OiffERENT!AL PRESSU~E VS. TIME FOR NODES 2,3,4 AND ~

(BREAK :N NODE 6) 237

REVISION 7 DECEMBER 1998 I :.

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REVISION 7 DECEMBER 1998 ftAINSTEAft LINE BREAK JN tND QUAD TUNNEL CHIDE 8 J tlodes e g lo

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REVISION 7 DECEMBER 1998 20.

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REVISION 7 DECEMBER 1998 nAJNSTERff LINE lftEAK JN ZND I. i If QUAD YUMNEL. (NBD£ "I ,

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REVISION 7 DECEMBER, 1998 fflU NBTERtt LINE BREllK JH 2ND ' urr QUAD TUNNEL rNftDE '1 l

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REVISION 7 DECEMBER 1998

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244 REVISION 7 DECEMBER 1998 10.0

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