ML17297A681
| ML17297A681 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/17/1981 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-04, REF-GTECI-A-09, REF-GTECI-A-11, REF-GTECI-A-12, REF-GTECI-EQ, REF-GTECI-RV, REF-GTECI-SG, REF-GTECI-SY, TASK-A-04, TASK-A-09, TASK-A-11, TASK-A-12, TASK-A-4, TASK-A-9, TASK-OR ANPP-18669-JMA, NUDOCS 8108190148 | |
| Download: ML17297A681 (4) | |
Text
REGULAT INFORMATION DISTRIBUTIOAOYSTEM (RIBS)
I ACCESSIO>>V NBR;8108190148 DOC ~ DATE': 81/08/17 NOTARIZED:. NO DOCK T' FACILi:STN 50-528 Palo Verde Nuc1 e'ar Stat ionF Uni t 1 g Ar i zona Publ i sTN-50-529 Pal o Verde Nucl ear stations Uni t 2F Ar i zona Publ i 05000529 STN-50-530 Palo Ve'rde. Nuclear Stations Uni t 3F, Ar i zona Publ i 05000530 AUTH,NAMK AUTHOR AFF ILIAT'ION VAN BRUNTE E>>,K.
Arizona Pub I i c Ser vi ce Co ~
REC IP ~ MAMEl REC IPIENT AFFIL>>I ATION TEDESCOF R ~ L>,
Assistant Director>> for Licensin9
SUBJECT:
-'dvises that items contained in NRC 810714 l trs re'nresolved S'afety Issues A-QFA-9qA 11 L A-12" 8 Questions 450
~ 12-450, 15: are more appropriately addr essed on CKSSAR docket by C-E ~
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'HOENIXs ARIZONA 85036 August 17, 1981 ANPP-18669 JMA/TFQ Mr. R. L. Tedesco Assistant Director for Licensing Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
g palo Verde Nuclear Generating gta (PVNGS) Unz.ts 1, 2 and 3
Docket Nos.
STN-50-528/529/530 File:
81-056-026 G.l.10 lg, Zy)
References:
(A)
NRC letter to E. E. Van Brunt, Jr.,
- APS, from R. L. Tedesco, NRC, dated July 14, 1981 "Unresolved Safety Issues Information Request" (B)
NRC letter to E.
E. Van Brunt, Jr.,
APS, from R. L. Tedesco, NRC, dated July 14, 1981 "Request for Additional Information PVNGS"
Dear Mr. Tedesco:
From our review of the referenced letters, we have determined that several of the items contained therein are more appropriately addressed on the CESSAR Docket (No. STN-50-470).
From Reference (A), Unresolved Safety Issues Information Request, the following should be addressed by CE:
2.
Steam Generator Tube Integrity (A-4) 3.
Anticipated Transients Without Scram (ATWS) (A-9) 4.
Reactor Vessel Materials Toughness (A-ll) 5.
Steam Generator and Reactor Coolant Pump Support (A-12)
Reference (B), Request for Additional Information-PVNGS, contained questions 450.12-450.15, from your Accident Evaluation Branch (AEB), which should also be addressed by CE.
Please contact me if you have any questions, or if you do not agree with our above assessment.
i8i08i90i48 8i08i7
'PDR ADOCK 05000528 A
'EVBJr/TFQ/av cc:
J. Kerrigan P. Hourihan A. C. Gehr C. Grimes Very truly yours E. E. Van Brun't, Jr.
APS Vice President, Nuclear Projects
+Oo ANPP Project Director 5
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