ML17306A186
| ML17306A186 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/04/1991 |
| From: | Conway W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17306A187 | List: |
| References | |
| 161.04192-WFC-G, NUDOCS 9110100166 | |
| Download: ML17306A186 (8) | |
Text
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TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9110100166 DOC.DATE: 91/10/04 NOTARIZED: YES DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit. 1, Arizona Publi 05000528 AUTH.NAME AUTHOR AFFILIATION CONWAY,W.F.
Arizona Public Service Co.
(formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards. application for amend to License NPF-41,changing I
Tech Specs Section 5.3.1, "Design Features of Reactor Core Fuel Assemblies."
Rept withheld (ref 10CFR2.790).
DISTRIBUTION CODE: APOID COPIES RECEIVED:LTR g ENCL $ SIZE:~+
TITLE: Proprietary Review Distribution Operating Reactor S
NOTES:STANDARDIZED PLANT 05000528 RECIPIENT ID CODE/NAME PD5 LA TRAMMELL,C COPIES LTTR ENCL 1
1 3
3 RECIPIENT ID CODE/NAME PD5 PD THOMPSON,M COPIES LTTR ENCL 1
1 3
3 D
D INTERNAL: ACRS OGC/HDS1 EXTERNAL: NRC PDR NOTES 6
6 1
0 O~
1 1
AEOD/DOA R
01 1
1 1
1 D
NOTE TO ALL"RIDS" RECIPIENTS:
A' D
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 19 ENCL 17
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,s'
WILLiAMF. CONWAY EXECVTIVEVICEPRESIDENT NUCLEAR Docket No.
STN 50-528 Arizona Public Service Company P.O. BOX53999
~
PMOENIX, ARIZONASS072<999 161-04192-MFC/GAM October 04, 1991 U.
S. Nuclear Regulatory Commission Attn: Document Control Desk Hail Station Pl-37 Washington, D.C.
20555
Dear Sirs:
Subj ect:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1 Proposed Technical Specification Change to Section 5.3.1 Design Features of the Reactor Core Fuel Assemblies File: 91-056-026; 91-005-419.5 In accordance with 10 CFR 50.90, Arizona Public Service Company (APS) submits herewith a request to amend Facility Operating License NPF-41, for PVNGS Unit 1.
The proposed amendment adds a
sentence to Technical Specifications, Design
- Features, Reactor Core Fuel Assemblies, Section 5.3.1, to allow the substitution of up to a total of 80 fuel rods clad with advanced zirconium-based alloys other than Zircaloy-4 in two fuel assemblies for in-reactor performance evaluation purposes.
Enclosure A includes:
B.
C.
D.
E.
F.
Description of Proposed Technical Specification Amendment Request Purpose of the Technical Specification Need for the Technical Specification Amendment No Significant Hazards Consideration Determination Safety Analysis for the Proposed Change Environmental Impact Consideration Determination Marked-Up Technical Specification Change Pages Enclosure B
includes five copies of a proprietary report entitled
~SaEee Evaluation Re ort for Use of Advanced Zirconium Based Claddin Materials in PVNGS Unit 1 Batch F Demonstration Fuel Assemblies, containing specific descriptions-of the elemental composition of eight advanced alloys and testing results.
In accordance with 10 CFR 2.790, ABB Combustion Engineering, the owner of this
- report, requests that this proprietary report be withheld in whole from public disclosure on the grounds that the specific alloy information in the report is considered to be confidential commercial information.
The affidavit required by 10 CFR 2.790 (b)(1) to sQpport this request for confidentiality is also included in Enclosure B.
Non-proprietary information from this proprietary report was used to prepare the Safety Analysis in Enclosure A.
9ii0i00i66 911004 PDR ADOCK 05000528
-P-PDR
t 161-04192-WFC/GAM October 04, 1991 U.
S. Nuclear Regulatory Commission Attn:
Document Control Desk Proposed Tech.
Spec.
Change to Section 5.3.1 Page 2
The Safety analysis in Enclosure A provides a basis for the conclusion that 10 CFR 50.46 criteria will be satisfied for the advanced alloys because the behavior of these alloys is expected to be essentially the same as that of conventional Zircaloy-4.
- However, an application for an exemption to 10 CFR 50.46 is included in Enclosure C, along with an exemption request for 10 CFR 50, Appendix K, and 10 CFR 50.44.
APS intends to install the two fuel assemblies containing advanced alloy clad fuel rods during the next Unit 1 refueling outage, scheduled to begin in February 1992.
The vendor does not intend to fabricate these fuel assemblies prior to NRC approval of this request.
Therefore, APS is requesting NRC approval by January 2, 1992.
APS is available to meet with the NRC Staff, if necessary, to support the review and approval of this amendment.
Pursuant to 10 CFR 50.91(b)(1),
a copy of the proposed amendment is being forwarded to the Arizona Radiation Regulatory Agency.
If you should have any questions, please contact Michael E. Powell of my staff at (602) 340-4981.
Sincerely, WFC/GAM/pmm Enclosures CC:
J.
B.
DE H.
AD C.
A. H.
C.
F.
Martin Coe Gehr Gutterman Tedford (all w/o Enclosure B)
'R
STATE OF ARIZONA
)
) ss.
COUNTY OF MARICOPA
)
I, E.
C.
- Simpson, represent that I am Vice President Nuclear Engineering, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true and correct.
E.
C. Simpson
, I, I
C,.
N t'ary'Public, l,i, Ih My Commission Expires hty Commission Expires Dec. 12, 1992
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