ML20113H205

Addendum 4 to LOCA Analysis Rept for Ja Fitzpatrick Nuclear Power Plant (Lead Plant)

ML20113H205
Person / Time
Site:	FitzPatrick
Issue date:	12/31/1984
From:	GENERAL ELECTRIC CO.
To:
Shared Package
ML20113H173	List: ML20113H172 ML20113H179 ML20113H186 ML20113H191 ML20113H205 ML20113H214
References
JPTS-85-002, JPTS-85-2, NEDO-21662-2, NEDO-21662-2-ADD04, NEDO-21662-2-ADD4, NUDOCS 8501250034
Download: ML20113H205 (8)

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l 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 FDR ~

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

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PUBLICATION NO. ERRATA And ADDENDA T. I. E. NO.

SHHT TITLE NO. 4 JAMES A. FITZPATRICK NUCLEAR December 1984 DATE POWER PLANT (LEAD PLANT)-

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

ISSUE DATE 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.

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-NEDO-21662-2

, LIST OF TABLES

. Table Title Page

'l ! .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 A

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~ NEDO-21662-2

3. INPUT TO ANALYSIS s s ' A: list of'the significant plant input parameters to the LOCA analysis is 1 . presented in Table 2.

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

? Plant Parameters:

. TCore Thermal Power 2531 MWt, which corresponds to

.c 105% of rated steam flow 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) 1.for Large Breaks - Discharge 2.37 ft 2 , 1.89 ft 2, 1,o ge 2 s - Suetion' 4.14 ft2

~ - Recirculation Line Break Area-1.0 ft2 0 .9 ft2, 0.15 ft2

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for Small Breaks ' Discharge

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

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,.  ? Peak Technical ' Initial

. 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 m =

JB.L" Initial - Type 3 7x7 .18.5 1.5 1. 2 .

'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-

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"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

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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.

.. 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' 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.

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The MAPLHGR

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

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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 coefficients: nucleate boiling prior to core uncovery, 25 Btu /hr-ft _ep 2 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 .

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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

-0.007 f40000- 9.0 1768

-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

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,, 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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