ML19350C625

Advises That Amend 56 to PSAR Was Filed in Anticipation of Preparation of Testimony Re Health & Safety Issues to Be Tried in May.Testimony Will Relate to Current Design for Plant.Psar Changes Encl.Related Correspondence

ML19350C625
Person / Time
Site:	Allens Creek File:Houston Lighting and Power Company icon.png
Issue date:	03/20/1981
From:	Copeland J BAKER & BOTTS
To:	Cheatum E, Linenberger G, Wolfe S Atomic Safety and Licensing Board Panel
References
NUDOCS 8104060474
Download: ML19350C625 (3)

Text

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BAKER & BOTTS

, CN E SMELL *LAZA houston, TEXA$ 77oo2 wA3HeNGTON OFFICE TELEX 76 2779 17 0 s

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March 20, 1981

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- ca issca escutAM 12 Sheldon J. Wolfe, Esq., Chairman Atomic Safety and Licensing Board Panel

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U. S. Nuclear Regulatory Commission - CD E Washington, D. C. 20555 g 4 Dr. E. Leon'rd a Cheatum G,

U093 gg Route 3, Box 350A Watkinsville, Georgia 30677 O MAR 2 61981 > '~

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g Cri:e cf $s Steefs y i Mr. Gustave A. Linenberger  :::Se.i,:: mice Atomic Safety and Licensing Emh f Board Panel 4

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l U. S. Nuclear Regulatory Commissicn G N i

Washington, D. C. 20555 Gentlemen:

In response to Judge Linenberger's question (Tr.

8877-78) concerning Amendment 56 to the PSAR, the amendment was filed in anticipation of.our preparation of testimony on the health and safety issues to be tried beginning in May.

The testimony will relate to the most current design for the plant. It was, therefore, deemed desirable to update the PSAR to be consistent with this. testimony.

Listed below are the PSAR changes (page i) ;

relevant contention; and brief reason for change:

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BAKER & BoTT3 Page 2 .

Fage Contention LContention # Change Delete return line 1.2-4 CRD return line Doherty 49 reference Bishop 6, Clarify analysis 2.2.A-13 LPG pipeline TexPirg AC 23 assumptions Board Commit to S50.44 3.1-46 Criterion 50 Questions 5 & 6 explicitly Delete return line 3.2-44 CRD return line Doherty 49 reference

~ Add concrete fill 3.8-21 Reactor pedestal Doherty 27 for steel pedestal-Doherty 17, Correct relief 5.2-14 SRV Reliability TexPirg AC 51 valve setpoints Reactor pressure 5.2-14 limits / relief valves TexPirg AC 41 Clarify insulation 5.4-3 ECCS sumps Dcherty 13 desi~gn Delete return line 5.4-3 CRD return line Doherty 49 reference Containment, :__ Eliptical to 6.2-3/5 Buckling .- Doherty 9 hemispherical dome Add suppression 6.3-14a ECCS sumps Doherty 13 pool strainer Rod pattern . Clarify RPCS 7.7-7/8/9 control system Doherty 12 operation Board Clarify. leakage 15.a-4b Bypass leakage Question 10 fractions All other changes were made to address the current GE fuel design and/or to make the Allens Creek PSAR compatible with this fuel data. These changes relate to the four fuel contentions on Flow Blockage - Doherty 25; Specific Enthalpy --

Doherty 3; Fuel Swelling - Doherty 39; and Gap Conductance -

Doherty 20(a).

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CAKER & BoTTS -

Page 3 Changes were made on pdges 4.6-9 and 10 to address current design on Scram Discharge Volume Float Switch (TexPirg AC 38); infornation on IGSCC was incorporated on 5.2-16/16a/

18a to be compatible with the GESSAR information used for Chapter 4. Both of the changes reflect the information con-tained in the affidavits submitted in support of Applicant's motions for summary disposition on the above-referenced con-tentions.

In addition, pages 5.2-3106, 31a and 33 were changed to list the correct edition of the ASME code used for the Pre-Service Inspection of the Reactor Vessel pre-sently being conducted.

Very truly yours, J. Gregory Copeland f

Attorney for Applicant Houston Lighting & Pcwer Company JGC/66 .

cc: All parties i ,

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