ML20086R720
| ML20086R720 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/21/1984 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20086R719 | List: |
| References | |
| 8150N, NUDOCS 8403010093 | |
| Download: ML20086R720 (18) | |
Text
-
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.s ATTACHMENT 1 i ..
Description of Proposed Changes to Technical Specification Figure 3.5-1
'l) Sheet 1 of 4: the top curve _contains the Barrier LTA MAPLHGR curve which-has been extended from 40,000 to 45,000 MWD /ST. The bottom curve contains the 8DRB265L/P8DRB265L MAPLHGR curve. This curve has
.been replotted on-a new' scale, but contains no changes from that presently in the Quad Cities Unit 1 Technical Specifications.
- 2. Sheet 3 of 4; the top curve contains the P8DRB239 MAPLHGR curve.
This1 curve has been replotted~on new scale, but contains no changes from that presently in the Quad Cities Unit 1 Technical
. Specifications. 'The bottom curve contains the P8DRB265H/BP8DRB265H MAPLHGR curve. -This curve has been relabeled to include fuel type
- BP8DRB265H.(barrier fuel otherwise-identical to P8DRB265H)and has
.been extended to 45,000 MWD /STU.
- 3. . Sheet 4 of 4; the top curve contains the P8DRB282 MAPLHGR curve.
This curve has' teen replotted on a new secle, but contains no chcrges
'from that presently in the Quad Cities Unit 1 Technical l Specifications. The bottom curve contains a new MAPLHGR curve for fuel type.BP8DRB283H.
All MAPLHGR curves contain revision bars to indicate changes from values currently in the Quad Cities Technical Specifications, r
s' 4
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i _
- r- ~'e403010093 840221
.PDR ADOCK 05000254
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p? ATTACHMENT 2
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Proposed Change to Appendix A , : Technical Specifications to-
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Operating License DPR-29
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- e Revised pages: . Figure 3.5-1 (Sheet 1 of 4) -
(Sheet 3 of.4)'
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(Sheet 4 of 4) (*' ' C;-; 5 /_ , sy af
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T. ATTACHMENT 3 Evaluation of Significant Hazards Consideration Description of-Amendment Request l Recent Errata and Addenda-to NEDO-24146A reflected extension of ' MAPLHGR curves to 45,000 MWD /ST for certain fuel types. This amendment , request reflects these_ changes. Basis for Proposed No Significant Hazards Consideration Determination Commonwealth Edison has evaluated the proposed Technical Specifi-cation 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 1 in accordance with the proposed amendments will nnt: 1)- involve a significant increase in the probability or consequences of an accident previously evaluated because: a) the amendments involve restrictions on the reactor power distribution during normal operation which of itself cannot
~ initiate an accident and therefore does not increase the
-probability of an accident and b) these restrictions ~on power distribution are based on a reanalysis or re-evaluation of accidents in accordance with NRC approved methods and are.specifically provided to ensure that the consequences of accidents (LOCA) remain within'the existing accident criteria established for Quad Cities.
- 2) create the possibilityLof a new or different kind of accident from any-accident previously evaluated for the same reason as
~(1)a. above and 3)) involve a significant reduction in the margin of safety since the Jamendments are specifically intended to ensure that the 10 CFR 50.46 ECCS criteria continue to be protected during future operation.
In-consideration of the above, Commonwealth Edison expects that NRC. approval of-these1 amendments should not be predicated on satisfactory l resolution of public comments or intervention as provided for by 10 CFR 50.91(a)(4). f
,- - q
e < ATTACHMENT-4 Errata and Addenda Nos. 10 thru.12 to NEDO-24146A " Loss-of-Coolant
.. Accident' Analysis. Report for Dresden Units 2,3 and Quad Cities Units
, .1, 2 Nuclear Power Stations".
-8150N
( _ I- s' s
- C'UCLE AD ENEM2Y BUSINESS OPE 7ATIONS o CENER AL ELECTulc COMPANY SAN JOSE, CALIFORNIA 96125 G EN ER AL $ ELECTRIC APPLICABLE TO:
'"C^*' " " ~ NEDO-2414 6 A 79NED273 ERRATA And ADDENDA T.1. E. N(s.
SHEET TITLE LOCA ANALYSIS REPORT FOR 10 NO. DRESDEN UNITS 2, 3 AND QUAD D fE April 1983 CITIES 1,2 NUCLEAR POWER STATIONS April 1979 Nom Cormn#wpierotthep#cs64 tSSUE DATE publication as specifiedbelow. REFERENCES f TE M EC N E ppnAGyA,.H LfNg;) (com mitC NS A AcosTOONS)
- 1. Page 4-11 Replace with new page 4-11.
4 PAGE 1 of 1 r . -, , ._ .-- - - . . .. . - - -
. . . NEDO-24146A Table 4I
- (~ -
MAPLHCR VERSUS AVERAGE PU AR EXPOS 1TRE
. PLANT: Dresden 2.3/ Quad Cities 1,2 FUEL TYPE: P8DR3282 Average Planar Exposure MAPLHGR PCT 0xidation (mwd /t) (kW/ft) (*F) Fraction 200 11.2 213.2. 0.029 1,000 11.2 2132 0.029 5,000 11.8 2183 0.033 10,000 12.0 2189 0.032 .
15,000 12.0 2199 0.033 20,000 11.8 2181 0.032 25,000 11.3 2110 0.025 30,000 11.1 2075 0.043
-35,000 10.4 1981 0.035 40,000 9.8 1886 0.021 NOTE: Credit taken for the effects of pre-pressurization of the fuel rods Table 4J NAPLHGR VERSUS AVERAGE PLANAR EXPOSURE l
PLANT: Dresden 2,3/ Quad Cities 1,2 FUEL TYPE: P8DRB265H/BP8DRB265H
]
Average Planar Exposure ~ MAPLHGR PCT 0xidation (mwd /t)- (kW/ft) (
- F)_ Fraction 200: 11.5 2163 0.032 12000 11.6 2171 0.032 5,000 11.9 2192 0.033 10,000 12.1 2198 0.033 15,000 12.1 2200 0.033 20,000 11.9- 2190 0.032 25,000' 11.3 2116 0.026
- 0.018 30,000. 10.7 2018 35,000 10.2 1934 0.022 40,000 ,,
- 9.6 ' 1835 0.009 ,
8.9 45,000, 1755 0.007
]
NOTE: Same as Table 41 4-11 (a i
-.e NUCLEAR ENERGY 8USINESS OPERATIONS o GENE',IAL ELECTRIC COMPANY SAN JOSF4 CALIFORNIA 96126 GENER AL $ ELECTRIC APPLicA8LE TO:
NEDO-24146A
'"'C^"" -
79NED273 E'RRATA And ADDENDA T.1. E. NO. SHERT TITLE LOCA ANALYSIS REPORT FOR g DRESDEN UNITS 2, 3 AND QUAD DA E December 1983 CITIES 1.2 NUCLEAR POWER STATIONS NOTE: Correct st/ copies of the applicable ISSUE DATE APRIL 1979 publiestion as specified below. REFERENCES ' INSMUCTIONS ITEM ,j5,E,CyO,%PAGE gg , (con AECTeoNS AND ADDITION $l
- 1. Page v/vi Replace with new page v/vi
- 2. Pages 3-1 and 3-2 Replace with new pages 3-1 and 3-2
- 3. Page 4-3 Replace with new page 4-3
- 4. Page 4-10 Replace with new page 4-10
- 5. Page 4-15/4-16 Add new page 4-15/4-16 (Change brackets in right-hand margin indicate areas where report has been revised.)
l 4 PAGE of {_
.- ~. .- - _
.,** 3
~ ~ '
.- NEDO-24146A LIST OF TABLES Table Title Pg 1 Significant Input Parameters to the Loss-of-Coolant Accident 3-1 2 Summary of Break Spectrum Results 4-5 3 LOCA Analysis Figure Summary - Non-Lead Plant 4-6 4A MAPLHCR Versus Average Planar Exposure (7D212 - No Cad.) 4-7 4B MAPLHGR Versus Average Planar Exposure (7D212L) 4-7
.4C MAPLHGR Versus Average Planar Exposure (7D230) 4-8 4D MAPLHGR Versus Average Planar Exposure (EEIC - Pu) 4-8 4E. ~ MAPLHGR Vcrsus Average. Planar Exposure (SD250) 4-9 4F MAPLHGR Versus Average Planar Exposure (8D262) 4-9 4G MAPLHGR.Versus Average Planar Exposure (8DRB265L) 4-10
-4H MAPLHGR Versus Average Planar Exposure (Barrier LTA) 4-10 4I -MAPLHGR Versus Average Planar Exposure (P8DRB282) 4-11 ,
4J MAPLHGR Versus Average Planar Exposure (P8DRB265H/BP8DRB265H) 4-11 4K- ~MAPLHGR Versus Average Planar Exposure (P8DRB239) 4-12 4L MAPLHGR Versus Average Planar Exposure (P8DGB284)* 4-12 4!! MAPLHCR Vetsus Average Planar Exposure (P8DGB263L)* 4-13 4N MAPLHGR Versus Average Planar Exposure (P8DGB263H)* 4-13 40 MAPIJIGR Versus Average Planar Exposure (P8DGB298)* 4-14 4P; MAPIJIGR Versus Average Planar Exposure (P8DRB265L) and (P8DGB265L)* 4-14
~
4Q- MAPLHGR Versus Average Planar Exposure (BP8DRB283H) 4-15 l i
- Barrier- fuel for the' Barrier Fuel Demonneration Program k
v/vi
NEDO-24146A
- 3. . INPUT TO ANALYSIS A list of the si8nificant 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 lba/h, which corresponds to 102% of rated power Vessel Steam Dome Pressure 1020 psia Recirculation Line Break Area 4.18 ft (DBA) for Large Breaks - Suction Number of Drilled Bundles- . . 156 Fuel Parameters: Peak Technical Initial Specification Design Minimum Linear Heat Axial Criti al Fuel Bundle Generation Kate Peaking Power Fuel Type Geometry (kW/ft) _, Factor _ Rat. A. 7D212 - No Gad 7x7 17.5 1.57 1.2 B. 7D212L '7x7 .17.5 1.57 1.2 C. .7D230 7x7 17.5 1.57 1.2
- D. .EEIC. Pu 7x7 17.5 1.57 1.2 E. 8D250 8x8 13.4 1.57 1.2 F. 8D262 8x8 13.4 1.57 1.2 G.' -8DRB265L 8x8 13.4 1.57 1.2 H. Barrier LTA. 8x8 13.4 1.57 1.2
-I. P8DRB282 8x8 13.4 1.57 1.2 ,
J; ?8DRB265H/BP8DRB265H 8x8 13.4 1.57 1.2
~
L K.. P8DRB239 8x8 13.4 - 1.57 1.2 To account for the'2% gncertainty in bundle power required by Appendix K, the SCAT calculation is performed with an MCPR of 1.18 (i.e.,1.2 divided by 1.01) for a bundie with an initial MCPR of 1.20, 3-1
"r .
NEDO-24146A Table 1 (Continued) Fuel Parameters: (Continued) Peak Technical Initial Specification Design Minimum Lineer Heat Axial . Critical Feel Bundle Generation Rate Peaking Power Fuel Type Geometry (kW/ft) 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. P8DGB298** '. 8x8 13.4 1.57 1.2 P. - P8DRB26."J. 8x8 13.4 1.57 1.2
~
P8DGB265L** Q. BP8DRB283H 8x8 13.4 1.57 1.2
** Barrier fuel for the Barrier Fuel Demonstration Program '
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{ L. . . , .4.5 RESULTS OF THE CHASTE ANALYSIS '
~ This code is used, with suitable inputs from the other codes, ro calculate the s
- 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 axisi plane , in a single fuel assembly. Iterative applications of CHASTE determine the maximum permisnible' planar power where required to ratisfy the requirements of 10CFR50.46 acceptance criteria. The' CHASTE results presented are: e-e . Peak Cladding Temperature versas time 3 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 Heat Generation Rate (MAPLHCR) versus Planar Average Exrosure.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 MAPLHGR values for each fuel type for D2,3/QC1,2 are presented in Tables 4A_through 4Q. )
. - 4.6 METHODS-In the following sections, :it will be useful to refer to the methods used cla analyze DBA,; 1arge breaks, and small breaks. For jet-pump reactors,
- these are defined as follows:
- a. L DBA Methods. LAMB / SCAT / SAFE /DBA-REFLOOD/ CHASTE. Break size: DBA.
'4-3 4
~~ ~
- v. ,
v. h - Table 4G MAPLMGk VERSUS AVERAGE PLANAR EXPOSURE PLANT: Dresden 2.3/ Quad Cities 1.2 , FIEL TYPI: 8 tie 3263L Average Planar Exposure NAPLEGR PCT 0xidation (mwd /t) _(kW/ft) ('F) Fractien l_ 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 21 54 0.030 30,000 10.7 2075 0.023
~
35,000 10. 2 ' , 200% 0.018 . 40,000 9.6 1913 0.013 Tabic 4H MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE PLANT: Quad Cities 1 FUEL TYPE: Barrier LTA 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 0.015 4-10
*'J "
NEDO-24146A Table 4Q. MAPLHCR VERSUS AVERAGE PLANAR EXPOSURE PLANT: Quad Cities 1 FUEL TYPE: BP8DRB283H
~
' Average Planar Exposure MAPLHGR PCT Oxidation (mwd /t) -(kW/ft) (*F) Fraction
, 200 11.2 2128 0.028 1,000' 11.2 2121 0.028
'- :5,000- 11.7 2157 0.030 10,000- 12.0 2192 0.033
.15,000 12.0 2199 0.033 20,000 11.9 2195 0.033 25,000 -11.4 2132- -
0.027 30,000 10.8 2051 0.038 35,000 10.3. 1956 0.031
~
40.000' 9.6' 1841 0.004 45,000. 9.0 1764 0.007 NOTE: Credit taken'for the effects of pre-pressurization of the fuel rods. I! e
- In 4-15/4-16
.$ 1 A
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.-- .. , _ _. ._ _ .,- . . , _ , , , . _ . _ , .. _ _ . ~ , _ . _ . . . . _ , _ . , . -
's NUCLEAR ENERGY SU$lNESS O,ER AT80N3 o GENERAL ELECTRP0 COMPANY SAN JOSE, CALIFORNIA 96126 GENER AL $ ELECTRIC APPLICABLE TO:
,UsuCATiON NO. NEDO-24146A T.1. E. NO. 79NED273 TIT u LOCA ANALYSIS REPORT FOR g.y DRESDEN UNITS 2, 3 AND QUAD DATE January 1984 CITIES 1,2 NUCLEAR POWER STATIONS
~~ ~
NOTE: Correct allcopies of the applicable ISSUE DATE APRIL 1979 publication as specifiedbelow. REFERENCES INSTRUCTIONS l EM ,{5,ECT ON L NC) ICORRECTIONS AND ADDITIONS) Ao APH
- 1. Page 4-10 Replace with new page 4-10 i <
l l (Change brackets in right-hand margin indicate l areas where report has been revised.) l 1 l . 9 PAGE I Of I
) <
v o--
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' . Table 4G MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE
( PLANT: Dresden 2,3/ Quad cities 1,2 FUEL TYPE: 80RB265L
~ Average Planar Exposure MAPLHGR PCT Oxidation (mwd /t) (kW/ft) ;['j(( Fraction 200 11.5 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 411 (
MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE PLANT: Quad Cities' 1 - FUEL TYPE: Barrier -LTA Average Planar
- Exposure MAPLHGR PCT 0xidation (mwd /t) __
(kW/ft) (*F) Fraction 200 11.6 2171 0.032 l. 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 p-30,000 .10.5 2029 0.019 40,000 9.3 1913 0.013 45,000 i, 8.6 1840 0.010 ](,
4-10 f -: -}}