ML20244A633
| ML20244A633 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/16/1979 |
| From: | Whitmer C GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905230047 | |
| Download: ML20244A633 (7) | |
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.May 16, 1979 nw.en s <6 V "m j
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NRC DOCKET 50-321-j D,.,~
4 OPERATING LICENSE DPR-57
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EDWIN I. HATCH NUCLEAR PLANT UNIT 1 4
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ERRATA SHEET TO NEDo-24175-j 4'
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H Enclosed.for'your information'and use^are forty (40): copies of Errata and Addenda Sheet.Ko. Into NEDG624175, Supplemental Reload, 7
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Licensing Submittal for Edwin I'.-. Hatch Nuclear' Plant Unit 1. Reload 3.
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. h'c, sThe fr'equired editorial correctionsiwere noted in the March 22,1979,
]j i-le'tter:of transmittal'for the reload 3 licensing' application and are
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- Suqrn to and subscribed befcre me this 16th day of May, 1979.
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PUBUCAJiON NO, EM ATA. AM ADDENDA.
79NED253' Tc i a. s"o-
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/ WT LICENSING SUBMITTAL FOR EDtiIN I.
March.1979 m.s.
DATE
! tW...o 1IATCH IMIT.1 RELOAD 3 cr;;ea Correct all copies of the applicable :
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NOTE:
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tssu'E DATE March 1979:
' publication as specified below,
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' REFERENCES INSTRUCTIONS gygy (SE CTION, PAG E '
(CC ARECTIONS AND ADDITIONS) -
PAR AG AAPH, UNE)
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- 0 PLANT-UNIQUE ITEMS' (14 1.
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Appendix.a
- Revisions to.Iaitial Conditions or Inputs:
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w Fuel. Loading Error LHGR:
Appendix B f
Appendix C l
Densification Power Spiking:
Appendix A
.l New Methods
. Fuel Loading Error:
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RELOAD FUEL BUNDLES (1.0, 3.3.1 and 4._01
,2.
Number, Drilled 4
Number Fuel Type, 1
68 68 Initial Core Type 1 36 Irradiated 36 Initici Core Type 2 32 32 Initial Core Type 3 92 92 8DB250 (Reload 1)
'168 1
168 8DRB265H (Reload 2) f 164 164 8DRB265H f
New 560 560 Total 1
REFERENCE CORE LOADING PATTERN (3.3.1__).
x 3.
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13,056 M/il/ t Nominal previous cycle exposure:
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15,7.40 mwd /t Assumed reload-cycle exposure:
Core' loading pattern:
Figure 1.
= CALCULATED COBE EFFECTIVE MULTIPLICATIO i
T-WORTH - NO VOIDS, 20*C (3.3.2.1.1 and 3.3.2.1.2)_
'4.
BOC keff 1.110 Uncontrolled 0.950 Fully Controlled 0.983 Strongest Control Rod Our
-R, Maximum increase in Cold Core Reactivity g
0.0036 with Exposure Into Cycle, dk 3)
STANDBY LIQUID CONTROL SYSTEM SHUTDOW i
5 Shutdown Margin (ak)
(20'C, Xenon Free)_
ppm 0.036 600 l
.l-t areas of discussion in " Generic Reload Fuel !.pplication,
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NEDE-24011-P-A, Revision 0, August
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6, RELOAD-UNIQUE TRAMSIENT ANALYSIS IIPUTS (3.3.2M.5 AND 5.2)
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Void coeHicient N/A* (c/% R o) _
-7.415/-s.269 g
Void Fraction (%)
.40.12 Doppler Coefficient N/A (c/*F)
-O.231/-0.219 Average Fuel Temperature (*7) 1397 j
Scram Worth N/A ($)
-39.79/-31.83
-Scram Reactivity vs Time Figure 2' 1
7.
RELOAD-UNIQUE GETAB TRANSIENT ANALYSIS INITIAL CONDITION PARAMETERS (5.2)'
7x7
-8x8/8x8R Exposure EOC4 EOC4 Peaking factors (local, 1.27/1.36/1.40 1.17/1.59/1.40 radial and axial)
R-Factor 1.081 1.051
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Bundle Power (MWt) 5.798 6.768 Bundle Flow 124.59 113.73 (103 lb/hr)
Initial MCPR 1.20 1.20
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SELECTED MARGIN IMPROVEMENT OPTIONS (5.2.2)
(1) Recirculation Pump Trip (RPT)
(2) Thermal Power Monitor (TPM) 9.
CORE-WIDE TRANSIENT ANALYSIS RESULTF (5.2.1)
Power Flow 4
Q/A P,1 b
ACPR Plant Transient Exposure
(%)
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(%)
(%)
(psia)
(psig) 7x7 8x8/8W8R
Response
TT w/o BP BOC-!OC4 104.1 100 168.0 102.0 1149 1180 0.06 0.10 Figure 3 1.oss of BOC EOC4 104,1 100 118.1 116.9 1014 1066 0.13 0.14 Figure 4 100* FV Heat'ing Teciwater BOC-EOC4 104.1 100 135.4 106.8 1127 1161 0.06 0.07 Figure $
Controller Failure
- N = Nuclear Input Data l
A = Used in Transient Analysis i
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Notes:
J, Rod Pattern'is l/4 core mirror.
symmetxic upper left quadrant
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2.
No. indicate number of notches withdrawn out of 48.
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Limiting rte Rod Pattern i
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}, "N' REGULATORY IflFORMATION DISTRIBUTION S'YSTEM (RIDSF
=ACCEGSION N6R: 7905230047 00C.DATE: 79/05/16 NOTARIZED: 'YES DOCKET #
FACIL:50-321 EDWIN I, HATCH NUCLEAR, PLANT, UNIT 1, GEORGIA _ POWER C 05000321 AUTH.NAME AUTHOR' AFFILIATION WHITMER,C F.
GEORGIALPOWER CO, o
RECIP NAME RECIPIENT AFFILIATION OFFICE OF NUCLEAR REACTOR REGULATION
SUBJECT:
FORWARDS ERRATA & ADDEflDA SHEET 1 TO NE00-24175, SUPPLEMENTAL RELOAD LICENSING SUBMITTAL, DISTRIBUTION: CODE: A001S COPIES RECEIVED LTR ff ENCL Yd SIZE:_.Y. ;__
TITLE: GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LIC NO7ES:. __....
RECIPIENT COPIES R E C I PI8E NT COPIES ID CODE /NAME LTTR ENC!.
ID CODE /NAME LYTR ENCL ACTION:
05 BC 046 #.3 7
7 li(dtiTIF3 8NTERNAL:
0 1
1 02.NRC PDR 1
1
~
I&C 2
2 14 TA/EDO 1
1 15 CORE PERP BR 1
1 16 AD SYS/PROJ 1
1 17 ENGR SR 1
1 18 REAC SFTY OR 1
1 19 PLANT SYS BR 1
1 20 EEB 1
1 21 EFLT TRT SYS 1-22 BRINKMAN 1
1 EXTERNAL: 03 LPDR 1
1 04 NSIC 1
1 23 ACRS 16 16 l
pS M *I l
1 l.
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.6 l
4 S
TOTAL NUM6 OF. COPIES REatlIPED: LTTP 38 ENCL 38 m _ _ER______