ML20113H205

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Addendum 4 to LOCA Analysis Rept for Ja Fitzpatrick Nuclear Power Plant (Lead Plant)
ML20113H205
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 12/31/1984
From:
GENERAL ELECTRIC CO.
To:
Shared Package
ML20113H173 List:
References
JPTS-85-002, JPTS-85-2, NEDO-21662-2, NEDO-21662-2-ADD04, NEDO-21662-2-ADD4, NUDOCS 8501250034
Download: ML20113H205 (8)


Text

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ATTACHMENT IV TO JPN-85-03 Loss-of-Coolant Accident Analysis Report for James A.

FitzPatrick Nuclear Power Plant (Lead Plant)

(JPTS-85-002) 4 New York Power Authority

' James A.'FitzPatrick Nuclear Power Plant Docket No. 50-333 8501250034 850116 PDR ADOCK 05000333 P

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NUCLEAR ENERGY BUSINESS OPERATIONS e GENERAL ELECTRIC COMPANY SAN JOSE. CALIFORNIA 95125 GEN ER AL $ ELECTRIC APPLICABLE TO:

PUBLICATION NO.

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ERRATA And ADDENDA T. I. E. NO.

SHHT 4

TITLE NO.

JAMES A. FITZPATRICK NUCLEAR December 1984 DATE POWER PLANT (LEAD PLANT)-

NOTE: Correct allcopies of the applicable July 1977 ISSUE DATE pub // cation as specified below.

REFERENCES INSTRUCTIONS ITEM (CORRECTIONS AND ADDITIONS)

PARAG APH L NE) 01 Page v/vi Replace with new page v/vi.

02 Page 3-1/3-2 Replace with new page 3-1/3-2.

03 Page 4-3 Replace with new page 4-3.

04 Page 4-11/4-12 Replace with new pages 4-11 and 4-12.

l I Of I PAGE L

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-NEDO-21662-2 LIST OF TABLES

. Table Title Page

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.BWR/4 With LPCI-Modification (Important LOCA/ECCS-Parameters) 2-3 2

~ Significant Input Parameters to the Loss-of-Coolant Accident 3-1

. 3 -~

Summary.of Break Spectrum Results 4-5

.4 -

LOCA Analysis Figure Summary - Lead Plant 4-6 i SA -

MAPLHGR Versus Average Planar Exposure 4-7 15B

'MAPLHCR,Versus Average Planar Exposure.

4-7 SC MAPLHGR Versus Average Planar Exposure 4-8 SD ~

MAPLHGR Versus Average Planar Exposure 4-8 SE

'MAPLHGR Versus Average Planar Exposure 4-9 5F MAPLHGR'Versus Average Planar Exposure 4-9

'5G-MAPLHCR Versus Average Planar Exposure 4-10 SH MAPLHGR Versus Average Planar Exposure 4-10 51

'MAPLHGR Versus Average Planar Exposure 4-11 SJ MAPLHGR Varsus Average Planar Exposure 4-11 5K' MAPLHGR Versus Average Planar Exposure 4 6' Single Failuce' Evaluation (Plants With LPCI Modification) 6-7

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~ NEDO-21662-2 3.

INPUT TO ANALYSIS s

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' A: list of'the significant plant input parameters to the LOCA analysis is

. presented in Table 2.

1

Table 2 SIGNIFICANT INPUT PARAMETERS TO THE rLOSS-OF-COOLANT ACCIDENT ANALYSIS'

? Plant Parameters:

TCore Thermal Power 2531 MWt, which corresponds to 105% of rated steam flow

.c Vessel Steam Output 10.96 x 106 lba/h, which corresponds to 105% of rated steam flow Vessel Steam' Dome Pressure 1055 psia Recirculation Line, Break Area

~(DBA) 2 2

2 1.for Large Breaks - Discharge 2.37 ft, 1.89 ft, 1,o ge s

- Suetion' 4.14 ft2

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- Recirculation Line Break Area-for Small Breaks

' Discharge 1.0 ft2

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E

.9 ft2, 0.15 ft2 0

- Suction-0.07'ft Number of Drilled Bundles All Fuel Parameters:

? Peak Technical

' Initial

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Specification.

Design Minimum Linear Heat Axial Critical-

Fuel Bundle Generation Rate Peaking Power-1 Fuel Type Geometry (kW/ft)
Factor, Ratio *

'A6 Initial - Type 2 7x7 18.5

. l. 5 '

1.2 JB.L" Initial - Type 3 7x7

.18.5 1.5

1. 2.

m

=

'C.

18D274H 8x8

~13.4 1.4'

1. 2 >

D.-

8D274L 8x8.

13.4 1.4 1.2 E.

8DRB265L--

8x8

.13.4 1.4 1.2-lF..

8DRB283

8x8' 13.4 1.4'

'l.2 rG.' LP8DRB265L

-8x8 13.4 1.4 1.2 5H..i P8DRB283 8x8

-13.4' l.4'

1.2-

<r' "4

JI; :P8DRB284H 8x8 13.4-1.4 l'. 2 NL TJ.. i P8DRB2991 8x8 13.4 1.4 1.2' 1K.

BP8DRB299 8x8-13.4 1.4 1.2-

  • To' account for:the 2% uncertainty in bundle power required by Appendix'K', the T SCAT calculation is performed with 'an MCPR of l.18 (i.e.,1.2 divided by l.02).

1for a~ bundle'with an initial MCPR of 1.20.

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NEDO-21662 t

=4.5 RESULTS OF-THE CHASTE ANALYS.IS 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

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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

' Peak Cladding. Temperature and Peak Local Oxidation versus Planar e

Average Exposure for the most' limiting break size e

Maximum Average Planar ! feat Generation Rate (HAPLHGR) versus Planar Average Exposure for the rost limiting break size e'

' Rod Perforation Time and Temperature e

Hot Rod Location A 'sussnary of; the analytical.results is given in Table 3.

Table 4 lists the cfigures provided for this analysis. The MAPLHGR values for each fuel type in

-the FitzPatrick core'are presented in Tables SA through 5K.

The MAPLHGR

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- values are based on the use of 100-mil channels except where noted.

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4-3 b

NEDO-21662-2 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. 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 ft < A < DBA.

c.

Small Break Methods (SBM). SAFE /non-DBA REFLOOD. Heat transfer 2

coefficients: nucleate boiling prior to core uncovery, 25 Btu /hr-ft _ep 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.

4-4 a

4

.1 NEDO-21662-2 Table SI-MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Plant': FitzPatrick Fuel Type: P8DRB284H Average' Planar

. Exposure MAPLHGR PCT 0xidation

'(mwd /t)

-(kW/ft)

(*F)-

Fraction 200~

11.3 2116 0.026 1000.

11.3 2117-0.026 15000-11.7' 2152

-0.029

~10000-12.1 2185 0.031 15000 12.0 2186 0.031 20000 11.6 2142 0.027 L25000 10.9 2046 0.020 3i00001 10.2 1945 0.014 35000:

9.6.

1852 0.010 f40000-9.0 1768

-0.007

-Table SJ MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Plant: FitzPatrick l Fuel Type: P8DRB299

Average Planar Exposure _

MAPLHGR.

PCT Oxidation (mwd /t)

(kW/ft)

.(*F)

-Fraction

!200 10.9 2068 0.022 1000

' 11. 0 -

'2072 0.023 J5000.

11.5 2111 0.025 10000.

12.2 2191 0.031 15000

'12.2:

2198 0.032 "di~'

20000 12.1-2195

'O.032

-25000 11.6-

'2139' O.02/

'30000 10.9 2029 0.019

-35000 10.3 1955 0.023 140000

'9.6-1836 0.009 M

I 4-11.

p..

A NED0-21662-2 Table SK:

MAPLHGR VERSUS AVERACE PLANAR EXPOSURE TPlant: Fitzpatrick Fuel Type: BP8DRB299*

. Average Planar-Expos _ure MAPLHGR PCT.

Oxidation (mwd /t)

(kW/ft)

(*F)

Fraction

-200

'10.9 2060 0.022

' 1,000' 11.0 2063 0.022 5,000 11.5 2106 0.0241 10,000E 12.2 2192 0.031' 115,000 12.2 2198 0.032 20,000-

' 12.1 -.

2197 0.032 25,000-

' 11. 5 '

2139 0.027

30,000, 11.0 2041

.0.019 35,000-10.3 1955 0.028 40,000.

-9.7' 1841.

0.009 45,000-9.0 -

1770 0.007-

  • 80 mil channel' thickness.

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