ML20148F144
| 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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M y 3 zgp Branch Reading JRBuchanan, ORNL Dock.t tio. 50-29 RAPurple, L:0R-1 h
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'Jankco Atode Lloctric Co pany OGC g[G:
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dr. L.11. licider ACRS (16)
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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-
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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
- h required to corglete our review.
The needed information and schedulen care diccussed with Mr. C. Andonnini of your staff during a discussion 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.
Sincerely, b?W
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MS Robert A. Purple, Chief 6
(f Operating Reactors Branch s1 Direct. orate of Licensing R?!
Caclocure:
@.I Attachucat A - Additional 6,n 2
Infore.ation on Yankee-Rowe hk W
Tills DOCUMENT CONTAINS Qf POOR QUA!JTY PAGES A
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1 ATTACIC-fEHT A 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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YANrJ.E AT0!fIC EEECTRIC CO!!P/Jn'.
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1.
Provide a deceription of the nov incore instrumentation pachace in
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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
A Specifications.
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 i.l to details shown in the present Fir.urce 107:4A and 107:4L.
b 3.
Describe in sufficient dotail the thit61c icak detection system and how you vill provide for isolation of individual thimbles.
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j 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.
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Provide conurance that it is unlikely that potentini flou-induced j
vibration of the thimbles in the upper plenut vill cause failurc
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, i of a thieble or a thitbic avageceal.
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Ancucinc a thitble were to fail and would be isolated, will the 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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