ML19281A286
| ML19281A286 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/31/1978 |
| From: | Brugge R, Henrikson P GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19281A285 | List: |
| References | |
| NEDO-24168, NUDOCS 7903090295 | |
| Download: ML19281A286 (17) | |
Text
NEDO 24168 78NED401 CLASSI e
DECEMBER 1978 G
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- w-A'l SUPPLEMENTAL RELOAD LICENSING 1
SUBMITTAL FOR MILLSTONE UNIT 1 RELOAD 6 a,
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NED0-24168 78hTD401 Class I December 1978 SUPPLEMENTAL RELOAD LICENSING SUBMITTAL FOR MILLSTONE UNIT 1 PILOAD 6 Prepared:
P. E. Henrikson Approved $
44( 9 7 R. O. Brugge, Manager Operating Licneses II NUCLE AR ENERGY PROJECTS DIVISION e GENERAL ELECTRIC COMPANY SAN JOSE, CALIFORNIA 95125 GENER AL h ELECTRIC P---
NEDO-24168 IMPORTANT NOTICE REGARDING CONTENTS OF THIS PEPORT PLEASE FEAD CAF3 FULLY This report u2s prepared by General Electric solely for Northeast Utilitice Service Company (NUSCO) for NUSCO's use with the U.S.
Nuclear Regulatory Comission (USNRC) for amending NUSCO's operating license of the Milletone 1 Nuclear Pouer Station.
The infomation contained in this report is believed by General Electric to be an accurate and true representation of the facts knoun, obtained or pw vided to General Electric at the time this report uas prepared.
I The only undertakings of the General Electric Company respecting information in this document are contained in the contract between Northeast Utilities Service Company and General Electric Company for nuclear fuel and related services for the nuclear system for i
l Milletone 1 Nuclear Pouer Station, dated April 14, 1967 and nothing contained in this document shall be construed as changing said contract, or for any purpose other than that for which it is intended, is not authorized; and uith respect to any such unauthor-ized use, neither General Electric Company nor any of the con-tributors to this document makes any representation or varranty (c: press or implied) as to the completeness, accuracy or useful-nees of the informtion contained in this document or that such use of such infomation my not infringe privately owned rights; nor do they assu~e any responsibility for liability or damage of any kind uhich may result from such use of such information.
T
NED0-24168 1.
PLANT-UNIQUE ITEMS (1.0'*
Setpoints of Pilot-Actuated S/R Valves: Appendix A Deviations from NEDO-240ll-P-A: Appendix A Load Line Limit Analysis, NEDO-21285-1, November 10 77.
Control Cell Core, NEDE-24067-P, November 1977.
Segmented Test Rod Bundle, NEDE-20592-4P, November 1977.
2.
RELOAD FUEL BUNDLES (1.0, 3.3.1 and 4.0)
Fuel Type Number Number Drilled Irradiated 7DB250 40 0
Irradiated 8DB262 148 0
Irradiated 8DB274H 124 0
Irradiated 8DB274L 120 0
New 8DRB265H 48 48 New SDRB265L 100 100 Total 580 148 3.
REFERENCE CORE LOADING PATTERN (3.3.1)
Nominal previous cycle exposure:
15,553 mwd /t Assuced reload cycle exposure:
16,766 mwd /t Core loading pattern:
Figure 1 4.
CALCULATED CORE EFFECTIVE MULTIPLICATION AND CONTROL SYSTEM WORTH -
NO VOIDS, 20*C (3.3.2.1.1 AND 3.3.2.1.2)
BOC keff Uncontrolled 1.114 Fully Controlled 0.954 Strongest Control Rod Out 0.986 R, Maximum Increase in Cold Core Reactivity with Exposure Into Cycle, ok 0.002
- (
) refers to areas of discussion in " Generic Reload Fuel Application,"
NEDE-240ll-P-A, Revision 0, August 1978.
1
NEDO-24168 5.
STANDBY LIQUID CONTROL SYSTEM SHUTDOWN CAPABILITY (3.3.2.1.3)
Shutdown Margin (ok)
(20*C, Xenon Free) ppm 600 0.036 6.
RELOAD-UNIQUE TRANSIENT ANALYSIS INPUTS (3.3.2.1.5 AND 5.2)
Void Coefficient N/A*(C/% Rg)
-7.35/-9.19 Void Fraction (%)
36.85 Dcppler Coef ficient N/A (c/%*F)
-0.2229/-0.2118 Average Fuel Temperature (*F) 1202 Scram Worth N/A ($)
-36.92/-29.54 Scram Reactivity vs Time Figure 2 7.
RELOAD-UNIQUE GETAB TRANSIENT ANALYSIS INITIAL CONDITION PARAMETERS (5.2) 7x7 8x8/8x8R Exposure EOC EOC Peaking f actors (local, radial, axial) 1.24 1.22 1,49 1.710 1.40 1.40 R-Factor 1.100 1.052 Bundle Power (MWt) 5.056 5.793 Bundle Flow (10 lb/hr) 112.51 100.40 Initial MCPR 1.27 1.34 8.
SELECTED MARGIN IMPROVEMENT OPTIONS (5.2.2)
None
- N = Nuclear Input Data A = Used in Transient Analysis 2
NEDO-24168 9.
C0hE-WIDE TPANSIENT ANALYSIS RESULTS (5.2.1)
ACPR Power Flow 4 Q/A s1 v
8x8/
Plant Transient Exposure
(%)
(%)
(%) (%) (psig) (psig) 7x7 8x8R Response Load Rejection BOC7-100 100 270 114 1192 1225 0.20 0.27 igure 3 without Bypass EOC7 Loss of 100*F BOC7-100 100 117 117 1033 1072 0.13 0.15 Figure 4 Feedwater EOC7 Heating Feedwater BOC7-100 100 109 106 1033 1072 0.06 0.07 Figure 5 Controller EOC7 Failure 10.
LOCAL ROD WITHDRAWAL ERROR (WITH LIMITING INSTRUMENT FAILURE) TRANSIENT
SUMMARY
(5.2.1)
Rod Rod Position Limiting Blcck (Feet ACPR MLHGR (kW/f t)
Rod ReadinR* Withdrawn)
]x]**
8x8/8x8R 7x7**
8x8/8x8R Pattern 105 3.5 0.12 15.7 Figure 6 106 3.5 0.12 15.7 Figure 6 107***
4.0
'.15 16.7 Figure 6 108 5.5 0.24 17.2 Figure 6 109 6.5 0.26 17.3 Figure 6 110 7.5 0.27 17.1 Figure 6 11.
OPERATING MCPR LIMIT (5.2) 1.34 (8x8/8x8R fuel) 1.27 (7x7 fuel)
- Indicates set point selecte.d
- All 7x7 on periphery
- RBM setpoint 3
NEDO-24168 12.
OVERPRESSURIZATION ANALYSIS Sly 3ARY (5.3)
Power Core Flow s1 y
Plant Transient
(%)
(%)
(psig)
(psig)
Response
MSIV Closure 100 100
'1243 1275 Figure 7 (Flux Scram) 13.
STABILITY ANALYSIS RESULTS (5.4)
Decay Ratio:
Figure 8 Reactor Core Stability:
0.70 Decay Ratio, x f*0 2
(Extrapolated Rod Block Line -
Natural Circulation Power)
Channel Hydrodynamic Performance Decay Ratio, x /*0 2
(Extrapolated Rod Block Line -
Natural Circulation Power) 8x8/8x8R channel 0.25 7x7 channel
<0.01 14.
LOSS-OF-COOLANT ACCIDENT RESULTS (5.5.2)
Reference:
Results for irradiated fuel are given in NEDO-24085,
" Loss-of-Coolant Accident Analysis Report for Millstone Nuclear Power Station Unit 1," December 1977.
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I NEDO-24168 14.
(Continued)
Fuel Type 8DRB265H Exposure MAPLHGR PCT 0xidation (HWd/t)
(kW/ft)
(*F)
Fraction 200 10.4 2199 0.052 1,000 10.4 2199 0.051 5,000 10.5 2198 0.049 10,000 10.6 2198 0.048 15,000 10.6 2200 0.048 20,000 10.5 2395 0.048 25,000 10.4 2198 0.049 30,000 10.4 2198 0.049 Fuel Type 8DRB265L Exposure ItAPLHGR PCT 0xidation (HWd/t)
(kW/ft)
(*F)
Fraction 200 10.4 2200 0.052 1,000 10.4 2199 0.051 5,000 10.5 2198 0.049 10,000 10.6 2196 0.047 15,000 10.6 2199 0.048 20,000 10.5 2195 0.048 25,000 10.4 2198 0.049 30,000 10.4 2198 0.049 15.
LOADING ERROR RESULTS (5.5.4)
Limiting Event:
Misplaced bundle (8DRB265 into 8DB262)
MCPR:
1.09 16.
CONTROL ROD DROP ANALYSIS RESULTS (5.5.1)
Maximum incremental control rod worth: 0.78% Ak.
5
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NEDO-24168 MMMMMMM MMMMMMMMM MMMMMMMMMMM CMMMMMMMMMMMMM CMMMMMMMMMMMMM CMMMMMMMMMMMMM CMMMMMMMMMMMMM i
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13 15 17 1r 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 F UE L TYPE A = 708250 E = 80RB266H B = 8D8262 F = 80RB26SL C = 8DB274H D
8DB274 L
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Figure 1.
Reference Core Loading Pattern 6
i 100 45 C
C - 678 CRD IN PERCENT 1 - PdOMIN AL SCRAM CURVE IN (-$)
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Scram Reactivity Curve 7
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1 VESSEL PRES RISE (PSI) 1 PE'UTRON ftUX 2 HVE Sul0 CE HEAT FLUX 2 RELIEF VALVE FLOW, CROUPS 1 & 2 150.
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Feedwater Controller Failure L
NEDO-24168 02 OG 10 14 18 22 26 57 47 0
0 39 20 20 37 0
8 4
35 34 20 32 31 0
10 0
27 16 18 32 NOTES
- 1. ROD PATTERN IS 1/4 CORE MIRROR SYMMETRIC UPPER LEFT QUADRANT SHOWN ON MAP
- 2. NUMBER INDICATES NUMBER OF NOTCHES WITHDR AWN OUT OF 48 B LANK IS A WITHDR AWN ROD 3 ERROR ROD IS (26.31)
Figure 6.
Limiting RWE Rod Pattern 11
a 1
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i-ilk ISEEl Tid (SECl Figure 7.
MSIV Closure
NEDO-24168 1.2 1.0 OB
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'n5 NATURAL O
CIR CULATION y 06 e
0 8
EXTRAPOLATED 04 ROD BLOCK LINE 0.2 1
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O 20 40 60 80 100 PERCENT POWER Figure 8.
Millstone Unit 1 Reload 6 Decay Ratio 13/14
NEDO-24168 APPENDIX A 1.
SETPOINTS OF PILOT-ACTUATED S/R VALVES Previous analysis used setpoints given in NED0-24067, November 1967. Reload-6 setpoints used in the analysis for the main body of this document are given below:
1 @ 1095 psig + 1%
1 @ 1110 psig + 1%
4 @ 1125 psig + 1%
2.
DEVIATIONS FROM NEDO-240ll-P-A Table 5 ' (Nonvarying Plant GETAB Analysis Initial Conditions) will be revised to reflect val;es actually used "or the analysis in the main body of this document.
The following values have changed:
Reactor Pressure:
1065 psia Inlet Enthalpy:
526.0 Btu /lb A-1/A-2
-