ML17297A762
| ML17297A762 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/26/1981 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| ANPP-18761-JMA, NUDOCS 8109020139 | |
| Download: ML17297A762 (8) | |
Text
REBUEARY INPORMATION DISTR IBUTII~ SYSTEM (RIDS)
ACCESSION< NBR'810 FACIL(tSTN~50~528 STN~50~529 STN>50 530 AUTH~,NAME" VAN BRUNTPEl,K<s REC IP ~ hlAMKt TEDESCOPR
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L'0201i39-DOC ~ DATEi. 81/08/26 NOTARIZED!'O 1T'; ¹ Pal o Ver deNucl cari Statloni Un) t ii Ar ozone Publ 05 Palo Verde Nuclear" Stations Unit 2r Ar)zona Publ
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Palo Ve'r de Nuclear" Station< Unit 3i Ar ozone Publ 05000530 AUTHOR AFFILIATION Ar)zona Public Service. Co.
REC1IPX ENT AFFILIATION Ass)stant Dire'ctor for LTtcens)n8
SUBJECT:
Advises that encl Questions" 450 F 16 L 450 '7 re. radiological consequence'nalysis transmitted w/810714 8
31 ltrsi r espectdvel year e, mor e appropriately addr essed
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P.o. BOX 21666 PHOENIX, ARIZONA85036 August 26, 1981 ANPP-18761 JMA/TFQ Mr. R. L. Tedesco Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation 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:
81-056-026 G.1.10 Ref:,
.(A)
Letter from R. L. Tedesco, NRC, to E. E. Van Brunt, Jr.
dated July 14, 1981, subject:
Request for Additional Information PVNGS (AEB)
(B)
Letter from R. L. Tedesco, NRC, to E. E. Van Brunt, Jr.
dated July 31, 1981, subject:
Request for Additional Information PVNGS (AEB)
Dear Mr. Tedesco:
From our-review of the referenced letters, we have determined that attached questions 450.16 and 450.17, transmitted through References (A) and (B),
respectively, are more appropriately addressed on the CESSAR Docket (No.
STN-50-470).;'lease contact me if you have any questions, or if you do not agree with our above assessment.
Very truly yo rs E.
E. Van Brunt, Jr.
APS Vice President, Nuclear Projects ANPP Project Director EEVBJr/TFQ/av Attachment cc:
J. Kerrigan (w/a)
C. Grimes,(w/a)
P. Hourihan (w/a)
A. C. Gehr (w/a) 8109020139 810826 PDR ADOCK 05000528, A
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The radiological consequence evaluation provided in CESSAR Section 15.6.2 are based upon assumptions which vary greatly
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from previous staff practice in the following areas:
- 1) The evaluations were performed using values which are less than the proposed technical specification limits for normal operation.
This is not acceptable to the staff because the technical specifications define the operating envelope under which the plant can operate without restriction.
Analyses using values less than the technical specifications do not verify that at the technical specification limits the plant would operate safely and that the radiological consequences would not exceed the staff acceptance criteria on radiological exposures.
- 2) The radiological consequence analysis of a steam generator tube rupture makes no mention of iodine spiking in the CESSAR document, and the Palo Verde docket uses a spiking factor of only 100.
I The staff position on an acceptable spiking factor is provided in SRP Section 15.6.3.
This section states that a spiking factor of 500 times the normal release rate of iodine from the fuel should be used.
- 3) The iodine transport in the steam generator is determined using CENPD-180 and its supplement.
The staff 'position on iodine ti ansport in the steam generator is defined in SRP Section 15.6.3 and is that the iodine transport should be determined using the methods and models described in NUREG-0409.
The CESSAR and Palo Verde dockets do not discuss the differences in the methods used to those'roposed in NUREG-0409.
Based upon the above discussion, the staff position is that the applicant provide an analysis of the radiological consequences of the steam generator tube rupture which assumes operation at the proposed technical specification values and describes the differ'ences between the models used and those presented in the staff Standard Review Plan.
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RP 15.6.2) 0 ACCIDENT EVALUATIQN BRANCH In the evaluation of the double-ended break of the letdown line outside containment-upstream of the letdown line control valve (CESSAR Section 15.6.5.2),
the staff has calculated the dose in accordance with SRP 15.6.2.
The result shows the EAB, 0-2 hr, thyroid dose to be 85 rems.
This value is more than'wice the acceptable limit of 30 rems as defined in SRP 15.6.2.
The staff position is that the maximum equilibrium fission product concentration given in the technical. specification be reduced from 4.7 pci/cc to the standard 1 pci/cc.
This measure will correspondingly reduce the dose to within acceptable levels.
State your intent regarding compliance with our position.