ML17046A571

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9 to Updated Final Safety Analysis Report, Table 15.3-1 Through 15.3-4
ML17046A571
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/30/2017
From:
Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17046A230 List: ... further results
References
LR-N17-0034
Download: ML17046A571 (7)
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Text

TABLE 15.3-1 SALEM UNIT 1 SMALL BREAK LOCA ANALYSIS TIME SEQUENCE OF EVENTS Break Spectrum (High T )

avg 4-inch 3-inch Break Occurs (sec) 0.0 0.0 Reactor Trip Signal (sec) 22.88 41.72 Safety Injection Signal (sec) 22.88 41.72 Safety Injection Begins (sec) 54.1 73.5 Loop Seal Venting (sec) 320 588 Top of Core Uncovered (sec) 540 922 Accumulator Injection Begins (sec}

810 1830 Peak Clad Temperature Occurs (sec) 883 1532 Top Of Core Covered (sec) 1300 2650 Results for the 2-inch break size High T Low T avg avg Break Occurs (sec) o.o 0.0 Reactor Trip Signal (sec) 188.84 55.21 Safety Injection Signal (sec) 188.84 55.21 Safety Injection Begins (sec}

220.5 91.0 Loop Seal Venting (sec}

1308 1448 Top Of Core Uncovered (sec) 1918 2152 Accumulator Injection Begins (sec)

N/A N/A Peak Clad Temperature Occurs (sec}

3275 3333 Top Of Core Covered (sec}

6630 6560 1 Momentary core uncovery occurred during prelude to Extended core uncovery was not experienced.

The excursion maintains clad temperatures well below 700°F.

1 of 1 SGS-UFSAR 2-inch 1.5-inch 0.0 0.0 188.84 104.02 188.84 112.76 220.5 144.5 1308 2604 1918 N/A1 N/A N/A1 3275 N/A 6630 N/A1 loop seal clearing.

momentary temperature Revision 24 May 11, 2009

TABLE 15.3-1a SALEM UNIT 2 SMALL BREAK LOCA ANALYSIS TIME SEQUENCE OF EVENTS Break Spectrum Break Occurs (sec)

Reactor Trip Signal (sec)

Safety Injection Signal (sec)

Safety Injection Begins (sec)

Loop Seal Clearing (sec}

Top of Core Uncovered (sec)

Accumulator Injection Begins (sec)

Peak Clad Temperature Occurs (sec)

Top Of Core Covered (sec)

SGS-UFSAR 4-inch 3-inch 0.0 o.o 14.9 26 14.9 26 46.9 58 311 535 644 723 881 2025 971 812 1293 2272 1 of 1 2-inch 0.0 63 63 95 1353 1727 N/A 2004 3638 Revision 24 May 11, 2009

TABLE 15.3-2 SALEM UNIT 1 INPUT PARAMETERS USED IN THE ECCS ANALYSES Parameter 1 7 Reactor core rated-thermal power ',

(MWt)

Peak linear power 1' 2 (kw/ft) 2 Total peaking factor ( F0T at peak Power shape FoH Fuel3 Accumulator water volume, nominal (ft 3/accumulator) 4 Accumulator tank volume, nominal (ft 3/accumulator)

Pumped safety injection flow Steam generator tube plugging level (%) 5 Thermal Design Flow/loop, (gpm)

Vessel average temperature, {OF)

Reactor coolant pressure, (psia}

Min. aux. feedwater flowrate/loop, NOTES 6

{lb/sec)

High Tavg 3411 12.812

2. 40 See Figure 1.65 17 X 17 850 1350 See Figure 25 82,500 580 2300 44.13 Low Tavg 3411 12.812 2.40 15.3-2 1.65 17 X 17 850 1350 15.3-3 25 82,500 566 2300 44.13 1

Two percent is added to this power to account for calorimetric error.

Reactor coolant pump heat is not modeled in the SBLOCA analyses.

2 This represents a power shape corresponding to a peaking factor envelope (K1zl) based on F~ =

2.40.

3 The Performance + fuel features analyzed included ZIRLOM cladding.

Zirc-4 cladding was analyzed and ZIRLO~ cladding was determined to be limiting. Results are not included in this report because the differences in PCT's between fuel cladding materials was insignificant.

The analysis bounds operation with PERFORMANCE + VANTAGE-5H, and STANDARD (275 psig backfill) fuels.

4 Accumulator gas pressure is consistent with Technical Specification minimum minus uncertainties.

5 Uniform.

6 Flowrates per steam generator.

7 Small Break LOCA Analysis was performed at 3411 MWt with 2 percent calorimetric uncertainty.

A subsequent evaluation has allowed an uprate to 3459 MWt due to calorimetric uncertainty reduction.

This increase in power does not change the ultimate analyzed core power and therefore, the uprated conditions were not explicitly analyzed.

As such, no changes are required to Table 15.3-2.

1 of 1 SGS-UFSAR Revision 24 May 11, 2009

TABLE 15.3-2a SALEM UNIT 2 INPUT PARAMETERS USED IN THE ECCS ANALYSES Parameter 1

Reactor core rated-thermal power, (MWt)

Peak linear power 1' 2 (kw/ft) 2 Total peaking factor (FaT at peak Power shape FoH Fuel3 Accumulator wa!ter volume, nominal (ft 3/accumulator}

4 Accumulator tank volume, nominal (ft 3/accumulator)

Pumped safety injection flow Steam generator tube plugging level (%) 5 Thermal Design Flow/loop, (gpm}

Vessel average temperature, {OF}

Reactor coolant pressure, (psia)

Min. aux. feedwater flowrate/loop, 6

(lb/sec) 3459 13.896 2.50 See Figure 15.3-2a 1.65 17 X 17 850 1350 See Figure 15.3-3a 10 82,500 566-577.9 2300 44.0 1 0.6 percent is added to this power to account for calorimetric error.

Reactor coo1ant pump heat is not modeled in the SBLOCA analyses.

2 This represnts a power shape corresponding to a peaking factor envelope (Ku~>) based: on FaT = 2. 502.

3 The Performance + fuel features analyzed included ZIRLO~ cladding.

The analysis bounds operation with PERFORMANCE + VANTAGE-5H, STANDARD and RFA (275 psig backfill) fuels.

4 Accumulator gas pressure is consistent with Technical Specification minimum minus uncertainties.

5 Uniform.

6 Flowrates per steam generator.

SGS-UFSAR 1 of 1 Revision 24 May 11, 2009

TABLE 15.3-3 SALEM UNIT 1 SMALL BREAK LOCA ANALYSIS FUEL CLADDING RESULTS Break Spectrum, (High Tavg) 4-inch 3-inch 2-inch 1.5-inch Peak Clad Temperature (oF}

1343 1508 1580 N/A1 Peak Clad Temperature Location (ft) 11.25 11.50 11.50 N/A Peak Clad Temperature Time (sec) 883 1532 3275 N/A Local Zr/H20 Reaction, Max (%)

0.1323 0.7343 1.5456 0.0333 Local Zr/H20 Reaction Location (ft) 11.25 11.50 11.75 11.00 Total Zr/H20 Reaction (%)

< 1.0

< 1.0

< 1.0

< 1.0 Hot Rod Burst Time (sec)

No Burst No Burst No Burst No Burst Hot Rod Burst Location {ft)

N/A N/A N/A N/A Results for the 2-inch break size High Tavg Low Tavg Peak Clad Temperature (oF}

1580 1558 Peak Clad Temperature Location (ft) 11.50 11.75 Peak Clad Temperature Time (sec) 3275 3333 Local Zr/H20 Reaction, Max

(%)

1.5456 1.3064 Local Zr/H20 Reaction Location (ft) 11.75 11.75 Total Zr/H20 Reaction (%}

< 1.0

< 1.0 Hot Rod Burst Time (sec)

No Burst No Burst Hot Rod Burst Location (ft)

N/A N/A 1

Momentary core uncovery occurred during prelude to loop seal clearing.

Extended core uncovery was not experienced.

The momentary temperature excursion maintains clad temperatures well below 700°F.

1 of 1 SGS-UFSAR Revision 24 May 11, 2009

TABLE 15.3-3a SALEM UNIT 2 SMALL BREAK LOCA ANALYSIS FUEL CLADDING RESULTS Peak Clad Temperature (oF}

Peak Clad Temperature Location (ft}

Peak Clad Temperature Time {sec)

Local Zr/H20 Reaction, Max

(%)

Local Zr/H20 Reaction Location (ft)

Total Zr/H20 Reaction (%)

Hot Rod Burst Time (sec}

Hot Rod Burst Location {ft)

SGS-UFSAR Break Spectrum 4-inch 3-inch 964 987 10.75 10.25 971 812 0.01 0.01 10.75 10.75

< 1.0

< 1.0 No Burst No Burst N/A N/A 1 of 1 3-inch w/

Annular Pellets 987 910 10.25 10.75 812 2004 0.01 0.00 10.75 11.00

< 1.0

< 1.0 No Burst No Burst N/A N/A Revision 24 May 11, 2009

TABLE 1 5. J-1]

TIME SEQUENCE OF EVENTS FOR COMPI.i;:':'J<,

J,o;::;~-1 OF FLOW EVENTS F-..ccident Undervoltage Event

{Jnde r f r*equency Sven t SGS-UFS!\\P.

Event All reactor cool an:

purnp~o begin to coast.

0. 0 Undervoltage rea~tor trip 0.0 Rods begin to dror Minimum DNBR occur:-:

3.4 Frequency decay is reduced

n:~.tnd RCS flow O.D Under frequency re,-H*t c) r L r 1. p Rods begin to drop Minimum DNBR occurs 1 of 1 1.?

1

  • 8 J.9 Revision 18 April 6, ?000
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