ML20148F144

Requests Addl Info Re Util 740318 Tech Specs Changes for New Incore Instrumentation Package Installation.Response Required by 740530

ML20148F144
Person / Time
Site:	Yankee Rowe
Issue date:	05/13/1974
From:	Purple R US ATOMIC ENERGY COMMISSION (AEC)
To:	Heider L YANKEE ATOMIC ELECTRIC CO.
References
NUDOCS 8011030845
Download: ML20148F144 (2)

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.! P iW DISTRIBUTION: 3 Docket File j AEC PDR  %

M y 3 zgp Branch Reading JRBuchanan, ORNL f,J:,

Dock.t tio. 50-29 RAPurple, L:0R-1 ABurger, L:0R-1 h

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'Jankco Atode Lloctric Co pany OGC Niib: dr. L.11. licider ACRS (16) g[G: ;)

Assistant Vice Precident TJCarter, L:0R j 20 Turnpike Road SVarga, L:RP , v, 1.'estooro, hansachusetta 015S1 KRGoller, L:0R f

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?!y lettar dated icrch 13, 1974, you cubr.itted chanacs to the 'Iechnical Specifications appended to Licence cio. DPR-3 that would allow installa-tion of a new incore instrut.:entation package for the Yankee-Rowe reactor. ](

y Uc have reviewed your subnittal and fouad that additional infort:ation is required to corglete our review. The needed information and schedulen care diccussed with Mr. C. Andonnini of your staff during a discussion *h on tbc telephona on April 16, 1974.  %

342 e.c:.acmunt A to thin letter identifies for the record the additional M aformation that we have requested durint; the recent to.lophone discussion.

In order to raintain our review schedule, we need acceptable responses [Ah not later than May 30, 1974. @

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MS Robert A. Purple, Chief 6 Operating Reactors Branch s1 Direct. orate of Licensing (f R

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Caclocure: @.I Attachucat A - Additional  :,

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Tills DOCUMENT CONTAINS Qf POOR QUA!JTY PAGES A w- --

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r AImITIONAL DIFOPliATION Oli YAhTJ'E-ROUE 1

TISTALIATION OF A MEU U! Cone DISTRU,'C2?TATION. PACKAGE DOCITT No. 50-29 y

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1. Provide a deceription of the nov incore instrumentation pachace in ( >

sufficient dots.11 cer:parabic to the description in t.hc present. pagen f.-

107:1 through 107:8, including Figure 1 included in the Technical 1 Specifications. A

2. Provide a figure or figurco that will depict the important details 4!

of the fluc thithic scaling system at the vessel ports cor.: parable to details shown in the present Fir.urce 107:4A and 107:4L.

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3. Describe in sufficient dotail the thit61c icak detection system and b how you vill provide for isolation of individual thimbles. y ,

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4. Travide the basis for your conclusion that the totc1 fiev nnd the .  !

flou distribution in the reactor vessel will not be changed cig- , i nificantly as a result of the installarionoof the nodified support i structure in the upper plcuum. T;

's . Justify the use of the conoseals and svagescals in the recctor vcsoci .

head port ascorblics as /JISI U18.2 Safety Ciuds I featuren.

t. Provide conurance that it is unlikely that potentini flou-induced -!

vibration of the thimbles in the upper plenut vill cause failurc j of a thieble or a thitbic avageceal. ,N , i s

7. Ancucinc a thitble were to fail and would be isolated, will the ,

kl thiehic up to the isolation valve be protected against potential 3j danano from missiles to precludo uncontrolled 1cchase of primary J @!

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