ML17305A691
| ML17305A691 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/16/1990 |
| From: | ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML17305A690 | List: |
| References | |
| NUDOCS 9004230276 | |
| Download: ML17305A691 (9) | |
Text
1.0 INTRODUCTION
AND
SUMMARY
This report provides ~ evaluation of the design and performance of Palo Verde Nuclear Generating Station Unit 2 (PVNGS-2) during its third cycle of operation at 100% rated core power of 3800 Mtlt and NSSS power of 3822 MWt.
Operating conditions for Cycle 3 have been assumed to be consistent with those of the previous cycle and ar summarized as full power operation under base load conditions.'he core will consist of irradiated Batch B,
C and D assemblies, along with fresh Batch E assemblies.
The Cycle 2 termination burnup has been assumed to be between 392.7 and 446 EFPD (Effective Full Power Days).
The second cycle of operation will hereafter be referred to in this report as the "Reference Cycle."
Reference 1-2 presented analyses for the Reference Cycle.
The safety criteria (margins of safety, dase limits, etc.)
applicable for the plant were established in Reference 1-1.
A review of all postulated accidents and anticipated operational occurrences has shown that the Cycle 3 core design meets these safety criteria.
The Cycle 3 reload core characteristics have been evaluated with respect to the Reference Cycle.
Specific differences in core fuel loadings have been accounted for in the present analysis.
The status of the postulated accidents and anticipated operational occurrences for Cycle 3 can be summarized as follows:
1.
Transient data are less severe than those of the Reference Cycle analysis; therefore, no reanalysis is necessary, or 2.
Transient data are not bounded by those of the Reference Cycle
- analysis, therefore, reanalysis is required.
90042"'0276 900416 PDR ADOCK 05000529 PDC
2.0 OPERATING HISTORY OF THE REFERENCE CYCLE The Reference Cycle began with initial criticality on May 15, I988.
Power Ascension began on May 23,
- 1988, and on May 30,
- 1988, the unit reached full power.
It is presently estimated that Cycle 2 wi 11 terminate on or about February 23, 1990.
The Cycle 2 termination point can vary between 392.7 and 446 EFPO to accommodate the plant schedule and still be within the assumptions of the Cycle 3 analyses.
2-1
3.0 GENERAL OESCRIPTION The.Cycle 3 core will consist of those assembly types and numbers listed in Table 3-1.
Sixty-nine Batch 8 assemblies and twenty-eight Batch C will be removed from the Cycle 2 core to make way For ninety-six fresh, Hatch E assemblies.
Thirty-six Batch C
and all Batch 0 assemblies now in the core will be retained.
One Batch B
assembly discharged at EOC1 will be reinserted into the cores'igure 3-1 shows the poison shim and zoning configuration for those assemblies.
The reload batch will consist of 24 type EO assemblies, 8 type El assemblies with 16 burnable poison shims'per
- assembly, 24 type E2 assemblies with 16 burnable poison shims per assembly, 8 type E3 assemblies with 16 burnable poison shims per assembly, 4 type E4 assemblies with 8 burnable poison shims per assembly, 20 type E5 assemblies with 12 bu'rnable poison rods per assembly, and 8 type P1E4 assemblies with 16 burnable poison rods per assembly.
These sub-batch types are fuel zone-enriched and their configurations are shown in Figure 3-2.
I'he loading pattern for Cycle 3, showing fuel type and location, is displayed in Figure 3-3.
Figure 3-4 displays the beginning of Cycle 3 assembly average burnup distribution.
The burnup distribution is based on a Cycle 2 length of 420 EFPD.
Control element assembly patterns and in-core instrument locations will remain unchanged from the Reference Cycle and are shown in Figures 3-5 A
3 B and Figure 3-6, respectively.
3-1
TASLE 3-1 PALO VERDE NUCLEAR GEHERAT IHG STAT IOH UH IT 2
Cycle 3 Core Loading Assembly Oesig-nation Humber of Assemblies Fuel Rods per Assembly Initi al Enrichment (w/o U-235)
Humber Shims/
Assembly Initial Shim Loading (gm 810/in) iotal Humber of Fuel Shia
- Rods, Rods 00 01 02 04 E3 E4 E5 ToTAL 36 32 20 16 28 20 241 208 12 224 12 184 52 168 52 168 52 168 52 172 52 172'2 184 52 168 52 168 52 168 52 176 52 172 52 168 62 2.78 1.92 3.30 2.78 4.02 3.57 4.02 3.57 4.02 3.57 3.57 3.09 3.57 3.09 3,57 3,09 4.03 3.70 4.
03'.70 3.70 3.40 3.70 3.40 4.03 3,70 3.70 3.40 3.90 3,60 3-2 16 16 16 12 12 16 16 16
'12 16
.018
.022
.020
.022
.008
.020
.016
.020
. 016
.012
.020
~016 208 12 8064 432 5888 1664 3360 1040 1344 416 2688 832 688 208 4816 1456 4416 1248 1344 416 4032 1248 1344 416 704 208 3440 1040 1344 416 i4732 16 320 128 256 48 336 128 384 128 32 240 128
Ft(war 3-j fit/~ FfKt) ~343EJLY l'tJE1.
LOAt)lNGS QaTK)THOL@ uu. WZ)O rWC~V SUO-IA~
EO ti Asaassollao Q i.O) <</s U t)5 8 ).10 <<)o U ~ t)5 Svt-IA'TOl I) i I Ass+elias
'<</ov t)$
8 ).10 r/0 V.t)5 g IlC ~ iL<<0) 'Qi~ Pin 4.014 Q I 10/ia Svl OAT@I Il ~
6 As~lies C) I 4) <</o V t)5 H ).10 <</0 U.t)$
~ Ii(.>L)0) 5hia tis 0 OII ~ I 10/ia svo-bklcH Is - i Assoaaliss 0 i.o) <</s V t)5 Q ) ~ 10 <</0 v t)5 g IiC ~ AL)D)
Shies tis 0.01t On I~ 10/is SVO-SATE C) ti Aa~llu Q ).10 <</o U't)S g ).iO <</0 V t)$
g I C
AL 0) 5hi~ tls 4.420 Os I ~ 10/in SUO IA~ C5 IO Aoooml isa Q ).14 <</o U t)$
@ ).i0 <</0 v t)5
+ 41( AL)0) 5ht ~ tis 0,0tO Os I 10/is SUS-BATCH P) F4 - 8 ASSc.MBUES Q
3 90 bio U-23S H
3 60 <<lo U-235 IIC AL)0) Shia tin 016 gni B iOIIN 4
FZGUaE 3-3 PYNGS UHZT 2 CYCLE 3 FUEL t@mGEHEHT C
00 00 03 01 pl C4 05 05 KO K3 01 C
E1 KL 01 C
K5 KZ 03 05 KZ E5 05 GO c,O 05 03
'5 05 EZ 02 00 01 03 K4 K3 05 05 K5 KZ 05 C
00 KZ 02 01 Qd 00 8
Asay
~l'
~
Shams Pin Knr)chments 4 ion)ng fuel Ping 0 P)ns 9/0 0 O<vs M/0 Shim
- Load1ng, 5-LO/<n Avg.
'to, ol'say.
A slav....it a...-..ewe EO E1 EZ K3 E4 K5 P164 0
16-1I5 16 8
12 16'34 L84 4.03 220 168 4.03 220 168 3.70 220 168 3.70 228 176 4 03 224 L72 3;70 220 168 3.90 52, 3.70 52 '.70 52 3.40 52 3.40 52 3.70 52 3.40 52 360
.016
.020
.015
.012
.020
,016 24 8
24 8
4 20 3.957 3.952 3.629 3.629 3.955 3.630 3.8~
3-5
- NUCLEAR OESIGN PHYSICS CHARACTERISTICS Fuel Mana ement The Cycle 3 core makes use of a low-leakage fuel management
- scheme, in which previously burned Batch C assemblies are placed on the core periphery.
Most of the fresh 8atch E assemblies are located throughout the interior of the core where they are mixed with the previously burned fuel in a pattern that minimizes power peaking.
With this loading and a Cycle 2 endpoint at 420
- EFPO, the Cycle 3
reactivity lifetime for full power operation is expected to be 430 EFPO.
Explicit evaluations have been performed to assure applicability of all analyses to a Cycle 2 termination burnup of between 392.7 and 446 EFPO and for a Cycle 3 length up to 456 EFPO.
Characteristic physics parameters for Cycle 3 are compared to those of the Reference Cycle in Table 5-1.
The values in this table are intended to represent nominal core parameters.
Those values used in the safety analysis (see Sections 7 and 8) contain appropriate uncertainties, or incorporate values to bound future operating
- cycles, and in all cases are conservative with respect to the values E
reported in Table 5-1.
Table 5-2 presents a summary of CEA reactivity wor ths and allowances for the end of Cycle 3 full power steam line break transient with a comparison to the Reference Cycle data.
The full power steam line break was chosen to illustrate differences in CEA reactivity worths for the two cycles.
5-1