ML20031A758
| ML20031A758 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/31/1981 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20031A757 | List: |
| References | |
| NEDO-24045-ERR, NEDO-24045-ERR-03, NEDO-24045-ERR-3, NUDOCS 8109250384 | |
| Download: ML20031A758 (5) | |
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'L NUCLE An ENECGY SUSINESS GOOUP e GENE AL E LECT 0lC COMPANY SAN JOSE, CALIFOZNI A 9512$
GENER AL h ELECTRIC APPLICABtE TO:
N' EDO-24045 ERRATA And ADDENDA 5HEET Loss-of-Coolant Accident m
3 7,7 g NO 4
Analysis Report for Cooper July 1981 OA E Nuclear Power Station NOTE. Correct att copies of the applicscle August 1977
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jfj ISSUE OATE INST R UCTIONS a m ac a"pd ofN g >
(Com atCTeoN5 AND AcostioN5) 1 Page v/vi Replace with revised pages v/vi.
2 Page 3-1/3-2 Replace with revised page 3-1/3-2.
3 Page 4-3 Replace with revised page 4-3.
4 Pages 4-11 & 4-12 Insert new pages 4-11 and 4-12.
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d A NEDO-24045 LIST OF TABLES Table Title Page 1
Significant Input Parameters to the Loss-of-Coolant Accident Analysis 3-1 2
Summary of Results 4-5 3
LOCA Analysis Figure Summary 4 -6 4A MAPLHGR Versus Average Planar Exposure 4-7 4B MAPLHGR Versus Average Planar Exposure 4-8 4C MAPLHGR Versus Average Planar Exposure 4-9 4D MAPLHGR Versus Average Planar Exposure 4-10 4E MAPLHGR Versus Average Planar Exposure 4-11 4F MAPLHGR Versus Average Planar Exposure 4-12 i
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NEDO-26045 3.
INPUT TO ANALYSIS A list of the significant plant input parameters to the LOCA analysis is presented in Table 1.
Table 1 SIGNIFICANT INPUT PARAMETERS TO THE LOSS-OF-COOLANT ACCIDENT ANALYSIS Plant Parameters:
j Core Thermal Power 2486 NWt, which corresponds to 105% of rated steam flow Vessel Steam Output 10.04 x 106 lbm/h, which corresponds to 105% of rated steam flow l
Vessel Steam Dome Pitssure 1055 psia l
Recirculation Line Break Area 2
for Large Breaks - Discharge 2.40 ft2 (DBA) 1.90 ft (80% DBA)
- Suction 4.10 ft Number of Drilled Bundles All Fuel Parameters:
Peak Technical Initial Specification Design Minimum Lin.r Heat Axial Critical Fuel Bundle Generation Rate Peaking Power Fuel Type Geometry (kW/ft)
Factor Ratio
- A.
IC Type 2 7x7 18.5 1.5 1.2 B.
IC Type 3 7x7 18.5 1.5 1.2 C,
8D250 8x8 13.4 1.4 1.2 D.
8D274 8x8 13.4 1.4 1.2 E.
8DRB283/P8DRB283 8x8 13.4 1.4 1.2 F.
P8DRB2oSL 8x8 13.4 1.4 1.2
- To account for the 2% uncertainty in bundle poser required by Appendix K, the SCAT calculation is performed with an MCPR of 1.18 (i.e.,
1.2 Jivided by 1.02) for a bundle with an initial MCPR of 1.20.
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NED0-24045 4.5 RESULTS OF THE CHASTE ANALYSIS This code is used, with suitable inputs from the other codes, to calculate the fuel cladding heatup rate, peak cladding temperature, peak local cladding oxidation, and core-wide metal-water reaction for large breaks. The detailed fuel model in CHASTE considers transient gap conductance, clad swelling and rupture, and metal-water reaction. The empirical core spray heat transfer and channel wetting correlations are built into CHASTE, which solves the transient heat transfer equations for the entire LOCA transient at a single axial plane in a single fuel assembly. Iterative applications of CHASTE determine the maximum permissible planar power where required to satisfy the requirements of 10CFR50.46 acceptance criteria.
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The CHASTE results presented are:
e Peak Cladding Temperature versus time j
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e Peak Cladding Temperature versus Break Area 1
e Peak Cladding Temperature and Peak Local Oxidation versus Planar Average Exposure for the most limiting break size e
Maximum Average Planar Heat Generation Rate (MAPLHGR) versus Planar Average Expesure for the most limiting break size
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A summary of the analytical results is given in Table 2.
Table 3 lists the figures provided for this analysis. The MAPLHGR values for each fuel type in the Cooper core are presented in Tables 4A through 4F.
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x NED0-24045 4.6 METHODS In the following sections, it will be useful to refer to the methods used to analyze DBA, large breaks, and small breaks.
For j et,., ump reaccors, these are defined as follows:
a.
DBA Methods. LAMB / SCAT / SAFE /DBA-REFLOOD/ CHASTE. Break size: DBA.
b.
Large Break Methods (LBM). LAMB / SCAT / SAFE /non-DBA REFLOOD/ CHASTE.
Break sizes:
1.0 ft2 < A < DBA.
c.
Small Break Methods (SBM). SAFE /non-DBA REFLOOD. Heat trancfer coefficients: nucleate boiling prior to core uncovery, 25 Beu/hr-ft
- F after recovery, core spray when appropriate. Peak cladding temperature and peak local oxidation are calculated in non-DBA-REFLOOD.
Break sizes: A < 1.0 ft i
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NEDO 24045 Table 4E MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Plant: Cooper Fuel Type.
8DRB283/P8DRB283 Average Planar Exposure MAPLHGR PCT 0xidation (Mwd /t)
(kW/ft)
(*F)
Fraction 200 11.2 2079 0.022 1,000 11.2 2073 0.021 5,000 11.8 2139 0.026 10,000 12.0 2152 0.027 15,000 12.1 2171 0.028 20,000 11.8 2135 0.027 25,000 11.3 2089 0.022 30,000 11.1 2064 0.020 35,000 10.4 1978 0.015 40,000 9.8 1896 0.011 e
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J NED0-24045 Table 4F MAPLHGR VERSUS AVERAGE PLANAR EXPOSUR.I Plant: Cooper Fuel Type: P8DRB265L Average Planar Exposure MAPLHGR PCT 0xidation
'(Mwd /t)
(kW/ft)
(*F)
Fraction,
200 11.6 2101 0.023 1,000 11.6 2106 0.023 5,000 12.1 2147 0.026 10,000 12.1 2137 U.025 15,000 12.1 2145 0.026 20,000 11.9 2127 0.024 25,000 11.3 2054 0.019 30,000 10.7 1970 0.014 35,000 10.2 1885 0.010 40,000 9.6 1792 0.007 4
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