ML20037A594
| ML20037A594 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/06/1978 |
| From: | Office of Nuclear Reactor Regulation |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003160030 | |
| Download: ML20037A594 (2) | |
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HEHORANDUM FOR:
R. Reid, Chief, Operating Reactors Branch No. 4
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Division of Operating Reactors (a
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- Acting Branch Chief. Engineering Branch e
Division of Operating Reactors U
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SUBJECT:
CRY 5TAL RIVER UNIT 3 - EARLY WITHDPAWAL OF SURVEILLANCE CAPSULE (TAC 7564)
Plant Nam:
CrystaluRiver Ur.it 3 NSSS Vendor: Dabcox and Wilecx Docket Nt=ter: '50-302'
-Operating Reactors 4anch and Project Manager: ORB-4, C. Nelson Engineerin; and Frejects Crarch Involvd:
Erainetring 3 ranch Due Date: July 7 1973 3
Review Status: Ceephts in a ic nce dated Pay 30, 1978, nerica Power C rporation sutmitted a Ted.nical Specifiation char.gc r ;arding the Crystal Riv;r 3 Curycillar.cc capsult removal ar.d installatior, schedule. Florida Pet;er prepcsed tha+. CR2 Ca, sule B be ramved at 270 EFPD b lica of at the end of c
the first fuel cycie and tr.at CR3 Caresules A. C E and Fbe installcd at 270 EF;D in lieu of at the end of the first fuel cycle.
Me have reviewed the reposed change in the surveillara. capsule removal and installation schedules ar.d conclude that it is acceptable. We note that Apper. dix H of 10 CFR Part 50 requirts the first capsule to be withdrawn when the.RT pT reaches 50*F or 1/4 of service life, whichener H
is earlier. For CR3 "a:50 F shift in IITg has already occurred..
. Therefore, withdrawaliof Capsule B at 270 0 will meet the requirement's
.of' Appendix H and will. provide the necessary infomation to check the.
temperature-pressure limit curves of. this plant. Also, the instal &4 tion s of capsules A,~C. E and F at 270 EFPD 'will give these espsules approximately.
200 EFPD of additional expcaure. This additional exposure will provide, m
us with radiation dar_ege acta on,these capsula materials at Blightly.
higher fluence levels than the; original schedule would. This additional exposure willL in ona way reduceithe usefu17 ness of the surveil 3ance data that will be;obtainedifroct these CR3 capsms
'Also - this : schedule
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change will not adversely affect the Irtegrated Reactor Vessel -
. Material Surveillance Program that Crystal. River 3 is comitted to.
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Contact:
K. Hoge 49-20050 cc:
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