ML17298A409
| ML17298A409 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde |
| Issue date: | 06/14/1983 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.13, TASK-A-49-.13, TASK-OR, TASK-TM ANPP-24608-WFQ, NUDOCS 8306170302 | |
| Download: ML17298A409 (8) | |
Text
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~ DATEe 83/06/14 NOTARIZED:; YES DOCKET'
.FAOIL:STN 50.528.lPalo Verde.Nuclear 'Stationi Uni<t ii Ai izona;Publ) 05000528
'STN 50.529'Pal o Verdi,Nucl ear "Stat) one Uni~t '2F, Arizona Publ) 05000529
'STN 50.530 jPal o Verdi Nucl ear 'Stationi Uni>>t 13i Arizona>>Publ i 05000530
'AUTH~ NAME AUTHOR AFFILIATION VAN BRUNTFG',E+
Arizona <<Public 'Service Co>
'REC I'P i NAME~
RECIPIENT AFFILIATION KNIGHTONgGB Licensing. <
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> 05>> t ,6 6 .,1-1 ,1 ~ 1 -1 >>BNL (AMDTS.ONlY) FEMA REP DIV 139 NRC )PDR "02" NTIS 1,1 ~ 1 1 1 ~ .1 1 1 )TOTAL NUMBER,OF !COPIES -REQUIRED: L<<TTR "50 ENCL-,07 r l I f K K ~ IIIII>>>,'I>t f'1 (ti Fh ', lt h Wh f 'l )will 1 'h "l <<XF K f lr >I lk ~ A) ll $ > I(t 1 4 li,l wI, 9 ff'>>,llf' I", '"1 F) h> I t lt\\ W Ch h W ~ t FO If ~ f ~ I w(hf >>I, W>l fr>> (l>>g K III 'll>'i >>f 1-"I> fi" fi) 'If' K '1 >>lit>, I I ~ > f.g WW.> 3 f)lfh f 'gk> i', ">f1 ~ O'K W fi I>'W F IW) lf F-W ll 'if if, K<>> 'i'kt( 1 I W tf I y ll' 't>>i If'>> f'K ff II>il ) lilrl i I I>>if>> I( Ii > i I ~ l 'il i i 1 >i >>>I h '>>I 1 K 'W I Jf 1 I 1 <<f p '4 W II Ih 11 11 Arizona Public Service Company P.o. SOX 21666 ~ PHOENIX, ARIZONA 65036 June 14, 1983 ANPP-24068 WFQ/TFQ Director of Nuclear Reactor Regulation Attention: Mr. George Knighton, Chief Licensing Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3
Docket Nos. STN-50/528/529/530 File:
83-056-026'.1.01.10
References:
(A)
(B)
(c)
NUREG-0737, "Clarification of TMI Action Plan Requirements" dated
- November, 1980.
CEN-189, "Evaluation of Pressurized Thermal Shock
. effects due to small break LOCA's with loss of feedwater for the C-E NSSS",
dated
- December, 1981.
LD-83-024, letter from A. E. Scherer, C-E to D.
G. Eisenhut, NRC, dated March 22, 1983.
Dear Mr. Knighton:
Item II.K.2.13 of Reference (A) required the performance of a detailed analysis of the thermal mechanical conditions in the reactor vessel during recovery from small break LOCA's with an extended loss of all feedwater.
In response to this item, the C-E Owner's Group prepared Reference (B).
Reference (C) indicates CEN-189 is applicable to the System 80 design, and CESSAR-F, Appendix B will be appropriately amended.
To supplement the generic report we are hereby submitting CEN-189, Appendix J, which provides PVNGS specific information associated with this issue.
This submittal only addresses PVNGS Unit 1.
We will provide a PVNGS Unit 2 and 3
supplement to CEN-189, Appendix J by the fourth quarter of 1983.
The PVNGS LLIR will be amended to reference this report.
Please contact me if you have any questions on this matter.
Very truly yours 830b170302 830b14 PDR ADQCK 05000528 PDR EEVBJr/TFQ/sp Attachment cc:
E.
A. Licitra A. C. Gehr E. E.
Van Brunt, Jr.
APS Vice President, Nuclear Projects ANPP Project Director
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June 14, 1983 ANPP-24068 WFO/TFg STATE OF ARIZONA
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COUNTY'F MARICOPA)
I, Edwin E. Van Brunt, Jr., represent that I am Vice President Nuclear Projects of Arizona Public Service Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority so to do, 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.
FW~,P Edwin E. Van Brunt, Jr.
Sworn to before me this day of 1983'.
My Commission expires:
MyCemnhsfon Spine Aprtl e. gyrr
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PVNGS LLIR II.K.2 COMMISSION ORDERS ON BABCOCK 6c WILCOX PLANTS (selected items applicable to PVNGS)
II.K.2.13 THERMAL MECHANICAL REPORT -- EFFECT OF HIGH-PRESSURE INJECTION ON VESSEL INTEGRITY FOR SMALL-BREAK LOSS-OF-COOLANT ACCIDENT WITH NO AUXILIARYFEEDWATER Position A detailed analysis shall be performed of the thermal-mechanical conditions in the reactor vessel during recovery from small breaks with an extended loss of all feedwater.
PVNGS Evaluation Refer to CESSAR Appendix B, Item II.K.2.13.
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