ML17298C087
| ML17298C087 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/25/1985 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| ANPP-32497-EEVB, NUDOCS 8504290381 | |
| Download: ML17298C087 (10) | |
Text
I REGULATOR'l NFORMATION DISTRIBUTION TEM (RIDS) r ACCESSION NBR:8504290381 DOC ~ DATEe 85/04/25 NOTARIZED'
, YES DOCKE(T~ 0 FACIL:STN,50 528 Palo Ve'rde Nuclear Stations Unjt 1~ Arizona Publi 05000528 STN 50-529 Palo Verde, Nuclear Station~
Unit 2< Ar)zona Publi 0500052$
STN 50 530 Palo Verde Nuclear Stationi Unit 3p Arizona Publi 05000530 AUTH BYNAME AUTHOR AFFILIATION VAN BRUNTiE'.ED Arizona Public Service Co.
RECIP ~ NAME RECIPIENT AFFILIATION KNI'GHTONg G ~ N ~
Licensing Branch 3
SUBJECT:
Forwards draft" change to FSAR Table. 6",2;1 3grevising, pressurizer compartment design wall loading fromm 54 psid.to 73 psid.Revised value evaluated 8, acceptable. Design crite'ria of FSAR Section 3 '
confirmed, DISTRIBUTI N CODE ~
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Arizona Nuclear Power Project P.o. BOX 52034 4
PHOENIX, ARIZONA85072-2034 Director of Nuclear Reactor Regulation Mr. George W. Knighton, Chief Licensing Branch No.
3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 ANPP-32497-EEVB/TFQ April 25, 1985
Subject:
Palo Verde Nuclear Generation Station (PVNGS)
Units 1, 2, and 3
Docket Nos.
STN 50-528(License No. NPF-34)/529/530 Pressurizer Compartment Design Mall Loading File:
85-056-026 G.1.01.10
References:
(1)
Letter from E. E.
Van Brunt, Jr.,
ANPP, to G.
W. Knighton, NRC, dated December 10, 1984 (ANPP-31395).
Subject:
(2)
Telecon with the NRC Staff on April 10, 1985.
Subject:
Pressurizer Compartment Design Wall Loading Re-Analysis.
Dear Mr. Knighton:
Enclosed for your information is a draft FSAR change to FSAR Table 6.2.1-3.
This FSAR change has been discussed with the NRC Staff during the Reference (2) telecon.
FSAR Table 6.2.1-3 is being revised to change the Pressurizer compartment design wall loading from 54 psid to 73 psid.
This revised value has been analyzed and found to be acceptable.
n The revision to Table 6.2.1-'3 was made for the following reasons.
Reference
('1) submitted changes to the FSAR whi'ch included a change to the pressurizer compartment peak pressure (refer to FSAR Table 6.2.1-2).
This change was prompted by modifications to the pressurizer compartment which provided for forced air circulation in the pressurizer compartment.
This reduced the vent area available for relieving steam and water to the containment building in the event of a pipe rupture inside the compartment.
The analysis resulted in a calculated pressurizer compartment peak differential pressure of 72.4 psid.
However, the pressurizer compartment design wall loading, presented in FSAR Table 6.2.1-3, was not updated to reflect this change.
The revised value of 73 psid has been evaluated and has been found to be acceptable.
Additionally, this analysis conforms with the design criteria of FSAR Section 3.8.
8504290381 850425 I
PDR ADOCK 05000528 P
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Mr. George W. Knighton, Chief Pressurizer Compartment Design Wall Loading ANPP-32497 Page 2.
If you have any questions on this matter, please contact Mr. W. F. Quinn of my staff.
Very truly your CLt~
n~
E. E.
Van Brunt, Jr.
Executive Vice President Project Director EEVB/TFQ/das cc:
E.
A. Licitra A. C. Gehr R. P.
Zimmerman (all w/a)
STATE OF ARIZONA
)
) ss.
COUNTY OF MARICOPA)
I, Edwin E.
Van Brunt, Jr.,
represent that I am Executive Vice President, Arizona Nuclear Power Project, 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.
Edwin E.
Van Brunt, Jr.
Sworn to before me this ~
day of My Commission Expires:
My Commission Expires Nov. 12, 19A8
, 1985.
p CP 7 Notary Public
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PVNGS FSAR CONTAINMENT SYSTEMS Table 6.2.1-3 PRINCIPAL CONTAINMENT DESIGN PARAMETERS Containment Parameter Peak Value Internal design pressure, psig 60.0 Design temperature, F
High mean during normal operation
- Maximum, DBA External design pressure loading, psig 120.0 300.0 4.0 Net free volume, ft 2.6 x 10-Design leak rate, percent free volume per day at 60.0 psig 0.1 Subcompartments Reactor cavity design wall loading, psst.d 110~a~
Steam generator compartment design wall loading, psid 30(a)
Pressurizer compartment design wall loading, psid a.
This value does not include the dynamic load fac-tors which were used in the design as described in section 3.8.3.3.l.4.
Amendment 5
6.2.1-6 August 1981
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