ML17303A779
| ML17303A779 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/18/1988 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 161-00809-EEVB, 161-809-EEVB, TAC-66784, NUDOCS 8803010470 | |
| Download: ML17303A779 (5) | |
Text
REGUL*l Y INFORMATION DISTR IBUTIO SYSTEM (RIDS)
ACCESSION NBR: 8803010470 DOC. DATE: 88/02/18 NOTARIZED:
NO DOCKET FACIL: STh -'SQ-52'P Palo Verde Nuclear Stations Unit 2i Arizona Publi 0500052'P AUTH. NAME AUTHOR AFFILIATION VAN BRUNT'. E.
Arizona Nuclear Power Prospect (formerly Arizona Public Serv RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards revised pages to Cycle 2 reload analysis rept.
Revised pages reflect changes due to coastdown of Unit 2>
Cycle
- 1. Explicit calculations performed to assure that Cycle 2 analyses remain bounded bg Cycle 1.
DISTRIBUTION CODE:
IE26D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: Startup Report/Refueling Report (per Tech Specs)
NOTES: Standardized plant.
05000529 RECIPIENT ID CODE/NAME PD5 L*
LICITRA. E COPIES RECIPIENT LTTR ENCL ID CODE/NAME 1
0 PD5 PD 2
2 DAVISi M COPIES LTTR ENCL 1
1 2
2 INTERNAL: ACRS NRR /P MAS/ILRB 12 RES/DRPS DIR RGN2/DRSS/EPRPB 5
5 A~R T,E ADV 1,
1
~~EP Qg 02 1
1 RGN5 FILE Of 1
1 1
1 1
EXTERNAL:
LPDR NSIC 1
1 1
1 NRC PDR 1
1 NOTES:
TOTAL NUMBER OF COPIES REGUI RED:
LTTR 21 ENCL 20
Docket No.
STN 50-529 Arizona Nuclear Power Project P.o. BOX 52034
~
PHOENIX. ARIZONA85072-2034 161-00809-EEVB/PGN February 18, 1988 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Document Control Desk
Reference:
Letter from E.
E.
Van Brunt, Jr.
(ANPP) to NRC dated 12/3/87 (161-00683).
Subject:
Submittal of the Reload Analysis Report for Unit 2, Cycle 2.
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Cycle 2 Reload Analysis Report File:
88-056-026 Attached please find revised pages to the referenced Reload Analysis Report.
The revised pages reflect changes due to the coastdown of Unit 2, Cycle l.
Explicit calculations were performed to assure that the Cycle 2 analyses remain bounded by the Reference Cycle (Cycle 1).
If you have any questions or require additional information, please call Mr. A.
C. Rogers at (602) 371-4087.
Very truly ours lu-~
E.
E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/PGN/cal Attachments cc:
0.
M. De Michele (all w/a)
A. C. Gehr G.
W. Knighton E. A. Licitra J.
B. Martin T. J. Polich 88030i0470 880218 PDR ADQCK 05000529 P
2.0 OPERATING HISTORY OF THE REFERENCE CYCLE The plant is currently in its first fuel cycle which began with initial criticality on April 18, 1986.
Power Ascension began on April 22, 1986 and on September 19, 1986 the. unit was declared in commercial operation.
It is presently estimated that Cycle 1 will terminate on or about February 21, 1988.
The Cycle 1 termination point can vary between 15,744 NMD/T and 3&~ NMD/T to accommodate the plant schedule and still be within the ssumptions of the Cycle 2 analyses.
5.0.
.NUCLEAR DESIGN 5.1 PHYSICS CHARACTERISTICS
)
5.1.,1 Fuel Management The Cycle 2 core makes use of a low-leakage fuel management
- scheme, in which previously burned Batch 8 assemblies are placed on the core periphery.
Host of the fresh Batch 0 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.'ith this loading and a Cycle 1 endpoint at 16,512 NWD/T, the Cycle 2 reactivity lifetime for full power operation is expected to be 16,945 MMD/T. Explicit evaluations have be n performed to assure applicability of all analyses to a Cycle 1 termination burnup of between 15,744 and ~M-MWD/T and for a Cycle 2 length up to BR@45 HWD/T.
(7,WOO Characteristic physics parameters for Cycle 2 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 reported in Table 5-1.
Table 5-2 presents a summary of CEA reactivity worths and allowances for the end of Cycle 2 full power steam line break transien. with a comparison to the Referenc Cycle data.
The full power steam line break was chosen to illustrate differences in CEA reactivity worths for the two cycles.