ML20215A545

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Errata & Addenda Sheet 14,replacing Pages v/vi,3-2,4-3,4-10, 4-15 & 4-16,to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Station
ML20215A545
Person / Time
Site: Dresden, Quad Cities, 05000000
Issue date: 08/31/1986
From:
GENERAL ELECTRIC CO.
To:
Shared Package
ML20215A501 List:
References
79NED273, NEDO-24143-ERR-14, NEDO-24146A-ERR, NEDO-24146A-ERR-14, NUDOCS 8610060119
Download: ML20215A545 (12)
v • d • e


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NED0-24146A LIST OF TABLES

/  !

Title Page Table __

Significant Input Parameters to the Ioss-of-Coolant Accident 3-1 1

Summary of Break Spectrum Results 4-5 2

LOCA Analysis Figure Summary - Non-Lead Plant 4-6 3

MAPLHGR Versus Average Planar Exposure (7D212 - No Gad.) 4-7 4A MAPLHGR Versus Average Planar Exposure (7D212L) 4-7 4B MAPLHGR Versus Average Planar Exposure (7D230) 4-8 4C MAPLHGR Versus Average Planar Exposure (EEIC - Pu) 4-8 4D MAPLHGR Versus Average Planar Exposure (8D250) 4-9 4E MAPLHGR Versus Average Planar Exposure (8D262) 4-9 4F MAPLHGR Versus Average Planar Exposure (8DRB265L) 4-10 4G MAPLHGR Versus Average Planar Exposure (Barrier LTA) 4-10 l 4H 41 MAPLHGR Versus Average Planar Exposure (P8DRB282) 4-11 l

4J MAPLEGR Versus Average Planar Exposure (P8DRB'265H/BP8DRB265H) 4-11 4K MAPLHGR Versus Average Planar Exposure (P8DRB239) 4-12 MAPLHGR Versus Average Planar, Exposure (P8DGB284)* 4-12 4L MAPLHGR Versus Average Planar Exposure (P8DGB263L)* 4-13 4M MAPLHGR Versus Average Planar Exposure (P8DGB263H)* 4-13 4N MAPI GR Versus Average Planar Exposure (P8DGB298)* 4-14 40 4P MAPIRGR Versus Average Planar Exposure (P8DRB265L) 4-14 and (P8DGB265L)*

MAPLHGR Versus Average Planar Exposure (BP8DRB283H) 4-15 4Q 4R MAPLHGR Versus Average Planar Exposure (BP8DRB282) 4-13 4S MAPLHGR Versus Average Planar Exposure (BP8DRB299) 4-16

  • Barrier fuel for the Barrier Fuel Demonstration Program o

v/vi

e

, . NFDO-24146A

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 Core Thermal Power 2578 MWt, which corresponds to 102% of rated power Vessel Steam Output 9.96 x 106 lbm/h, which corresponds to 102% of rated power Vessel Steam Dome Pressure 1020 psia Recirculation Line Break Area 4.18 ft (DBA) s for Large Breaks - Suction

, Number of Drilled Bundles 156 Fuel Parameters:

Peak Technical Initial Specification Design Minimum Linear' Heat Axial Critical Fuel Bundle Generation Mate Peaking Power Fuel Type Geometry (kW/ft) ,

Factor Ratio

  • A. 7D212 No had 7x7 17.5 1.57 1.2 B. 7D212L 7x7 17.5 1.57 1.2 i C. 7D230 7x7 17.5 1.57 1.2 1.57 1.2 l D. EEIC - Pu 7x7 17.5 E. 8D250 8x8 13.4 1.57 1.2 l

F. 8D262 8x8 13.4 1.57 1.2

! G. 8DRB265L 8x8 13.4 1.57 1.2 i H. Barrier LTA 8x8 13.4 1.57 1.2 I. P8DRB282 8x8 13.4 1.57 1.2 I J. P8DRB265H/BP8DRB265H 8x8 13.4 1.57 1.2

~

K. P8DRB239 8x8 13.4 1.57 1.2 i To account for the 2% uncertainty in bundle power required by Appendix K, the l SCAT calculation is performed with an MCPR of 1.18 (i.e., 1.2 divided by 1.02)

for a bundle with an initial MCPR of 1.20.

I

! 3-1

[

e NEO-24146A ,

Table 1 (Continued)

Fuel Parameters: (Continued)

Peak Technical Initial Specification Design Minimum Linear Heat Axial Critical Fuel Bundle Generation Rate Peaking Power Fuel Type Geometry (kWft) Factor Ratio L. P8DGB284** 8x8 13.4 1.57 1.2

~

M. P8DGB263L** 8x8 13.4 1.57 1.2 N. P8DGB263H** 8x8 13.4 1.57 1.2

0. P 8 DGB298** 8x8 13.4 1.57 1.2 P. P8DRB265L/ 8x8 13.4 1.57 1.2 P8DGB265L**

Q. BP8DRB283H 8x8 13.4 1.57 1.2 R. BP8DRB282 8x8 13.4 1.57 1.2 S. BP8DRB299 8x8 13.4 1.57 1.2 .

    • Barrier fuel for the Barrier Fuel Demonstration Program e

I 3-2

r 8 NEDO-24146A 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 sin 61 e 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.

The CHASTE results presented are:

e Peak Cladding Temperature versus time e Peak Cladding Temperature versus Break Area e Peak Cladding Temperature and Peak Local Oxidation versus Planar Average Exposure for the most liiniting break size

~

e Maximum Average Planar Heat Generation Rate (MAPLHGR) versus Planar Average Exposure for the most limiting break size A summary of the analytical results is given in Table 2. Table 3 lists the figures provided for this analysis. The MAPIRGR values for each fuel type -

for D2,3/QC1,2 are presented in Tables 4A through 4S. .

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 jet-pump reactors, these are defined 'as follows:

a. DBA Methods. LAME / SCAT / SAFE /DBA-REFLOOD/ CHASTE. Break size: DBA.

l 4-3 i

- . - - - , .- .- - - - - , - ,y--- ----.,,-- -- ,--.,,n -

- HEDG-24146 .

b. Large Break Methods (LBM). LAMB / SCAT / SAFE /non-DBA PEFLOOD/ CHASTE.

2 Break sizes: 1.0 ft 1 A < DBA.

l ..

! b. Small Break Methods (SBM). SAFE /non-DBA REFLOOD. Heat transfer l coefficients: nucleate i, oiling prior to core uncovery, 25 Btu /hr-ft *F after recovery, core spray when appropriate. Peak ,

cladding temperature and peak local oxidation are calculated in 2

non-DBA-REFLOOD. Break sizes: A i 1.0 fe .

t o

4-4

b * -

NEOG-2414:A e

Table 4E MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE PLANT: Dresden 2,3/ Quad Cities 1,2 FUEL TYPE: 8D250 Average Planar Exposure MAPLHGR PCT Oxidation (mwd /t) (kW/ft) (*F) Fraction 200 11.2 2106 0.024 1,000 11.3 2109 0.024 5,000 11.9 2169 0.029 10,000 12.1 2179 0.029 15,000 12.2 2198 0.031 20,000 12.0 2199 0.031

~

25,000 11.5 2148 0.027 30,000 10.6 2020 0.017 35,000 9.6 1888 0.011 40,000 9.0 1808 0.008 Table 4F MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE PLANT: Dresden 2,3/ Quad Cities 1,2 FUEL TYPE: 8D262

. /

Average Planar Exposure MAPLHCR PCT 0xidation (mwd /t) (kW/ft) (*F) Fraction 200 11.1 2104 0.024 1,000 11.3 2107 0.024 5,000 11.9 2166 0.029 10,000 12.1 2175 0.029 15,000 12.2 2199 0.031 20,000 12.0 2199 0.032 25,000 11.6 2157 0.028 20,000 10.7 2042 0.019 35,000 9.8 1915 0.012 40,000 9.2 1831 0.009 4-9

(

NEDO-24146A .

9 Table 4G MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE PLANT: Dresden 2,3/ Quad Cities 1,2 .7UEL TYPE: 8DRB265L Average Planar Exposure MAPLHGR PCT 0xidation" (mwd /t) (kW/ft) (*F) Fraction 200 11.6 2189 0.035 1,000 11.6 2188 0.034 5,000 11.8 2198 0.034 10,000 11.9 2196 0.033 15,000 11.9 2198 0.034 20,000 11.7 2195 0.034 25,000 11.3 2154 0.030 30,000 10.7 2075 0.023 35,000 10.2 2002 0.018 40,000 9.6 1913 0.013 Table 4H MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE PLANT: Quad Cities 1 - FUEL TYPE: Barrier LIA Average Planar Exposure MAPLHGR PCT 0xidation (mwd /t) (kW/ft) (*F) Fraction 200 11.6 2171 0.032 1,000 11.6 2178 0.033 5,000 12.0 2198 0.034 10,000 12.1 2195 0.033 15,000 12.0 2200 0.033 20,000 11.7 2187 0.032 25,000 11.0 2115 0.025 30,000 10.5 2029 0.019 40,000 9.3 1913 0.013 45,000 8.6 1840 0.010 -

50,000 8.0 1785 0.009 55,000 7.3 1730 0.007 _

i 4-10 L

l

  • j-

. NEDO-24146A Ta.ble 4Q MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE PLANT: Quad Cities 1,2 FUEL TYPE: BP8DRB283H Average Planar Exposure MAPLHGR OfWd/t) PCT 0xidation (kW/f t) (*F) Fraction 200 11.2 1,000 2128 0.028 11.2 2121 5,000 11.7 0.028 2157 10,000 12.0 0.030 15,000 2192 0.033 12.0 2199

'20,000 0.033 11.9 2195 25,000 11.4 0.033 i 30,000 2132 0.027 10.8 2051 35,000 10.3 0.038 40,000 1956 0.031 9.6 1841 45,000 9.0 0.009 1764 0.007 NOTE:

Credit taken for the effects of pre-pressurization of the fuel rods.

Table 4R -

MAPLHCR VERSUS AVERAGE PLANAR EXPOSURE PLANT: Quad Cities 1,2 FUEL TYPE: BP8DRB282 Average Planar Exposure MAPLHGR PCT 0xidation (mwd /t) (kW/ f t) (*F) _ Fraction 200 11.2 1,000 2131 0.029 11.2 2128 0.028 5,000 11.8 2178 10,000 0.032 12.0 2188 0.032

, 15,000 12.1 20,000 2199 0.033 11.9 2192 0.033 l 25,000 11.4

{ 30,000 2129 0.027 10.8 2047 0.038 35,000 10.3 1957 0.031 40,000 9.6 1840 0.009 45,000 8.9 1761 0.007 NOTE: Credit taken for the effects of pre-pressurization of the fuel rode. ,

(

4-15

, _ ~ . . - ,

s NEDO-24146A Table 4S MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE: BP8DRB299 PLANT: Quad Cities 1&2 Average Planar MAPLHGR PCT 0xidation Exposure (kW/ft) (*F)_ Fraction (mwd /t) 200 10.90 2089 0.025 1,000 11.00 2090 0.025 5,000 11.50 2126 0.027 10,000 12.10 2199 0.033 15,000 12.10 2198 0.033 20,000 11.90 2197 0.033 25,000 11.50 2157 0.030 30,000 11.00 2072 0.049 35,000 10.30 1977 0.035 40,000 9.70 1879 0.021 45,000 9.00 1777 0.007 NOTE: Credit taken for the effects of pre-pressurization of the fuel rods. .

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4-16

ATTACHMENT 5 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION I DESCRIPTION OF AMENDMENT REOUEST commonwealth Edison proposes to amend Facility Operating License DPR-30 for Quad cities Unit 2 to support the Cycle 9 core reload. The proposed changes include:

1) Incorporation of the Cycle 9 Minimum Critical Power Ratio (MCPR) limit determined by the Cycle 9 transient analyses.
2) Addition of Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limits for the reload fuel and extension of existing limits to 40,000 MWD /t for fuel type BP8DRB282.
3) Deletion of existing License condition addressing Single Loop Operation (SLO) and incorporation of SLO in the body of the Technical Specifications.

Basis for Proposed No Significant Hazards Consideration Determination Commonwealth Edison has evaluated the proposed Technical Specification amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92(c), operation of Quad Cities Unit 2 Cycle 9 in accordance with the proposed amendments will not:

A. involve a significant increase in the probabilfty or consequences of an accident previously evaluated because:

1&2) The incorporation of the MCPR and MAPLHGR limits noted above is explicitly provided to establish limits on normal reactor operation which ensure that the core is operated within the assumptions and initial conditions of previous accident analyses. Operation within these limits will assure that the consequences of the affected accident, the Loss of Coolant Accident, remain with the results of the previous analyses. These limits were generated using analytical methods previously approved by the NRC. The probability of an accident is not affected by this change because no physical systems or equipment which could initiate an accident are affected.

3) The proposed SLO provisions are explicitly based on analyses performed by General Electric using NRC approved methods, to determine required adjustments in operating restrictions (MCPR, MAPLHGR) for SLO. Operation within the proposed SLO limits has been previously analyzed to assure that the

! consequences of accidents are not increased. The probability of an accident is not increased because operation in single loop has been previously approved for Quad Cities and has no causal relationship with the equipment or system failures necessary to initiate an accident.

B. Create the possibility of a new or different kind of accident from any accident previously evaluated because:

l 1&2) The proposed MCPR and MAPLHGR limits represent limitations on core power distribution which do not directly affect the operation or function of any system or component. As a result, there is no impact on or addition of any systems or equipment whose failure could initiate an accident.

, 3) SLO has been previously analyzed and approved for Quad i Cities.

C. Involve a significant reduction in the margin of safety because

all of the proposed changes have been analyzed to demonstrate that

! the consequences of transients or accidents are not increased j beyond that previously evaluated and accepted at Quad Cities.

I Based on the above discussion, Commonwealth Edison concludes that the proposed amendments do not represent a significant hazards consideration.

2072K

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