ML19330C355
| ML19330C355 | |
| Person / Time | |
|---|---|
| Site: | 05000124 |
| Issue date: | 03/20/1969 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19330C354 | List: |
| References | |
| NUDOCS 8008080278 | |
| Download: ML19330C355 (3) | |
Text
{{#Wiki_filter:. 9 Vircinin ?rd.jte: nic ~t.etitu*.c Docke-Nc. 50 l?4 Amend.ent No. 2 r ac.< 3.ity. icense .o..a-s2 a ......., n. \\,1S.. C.:. B.:.. V.'.C R. yC2.. .,.G m ws. n u -....> s.. .,,,. v.A..w,... =>.:., cm. e m.. - --,.. - tr.,3 e..e V Af ivdT v.. D W1ood.wv.4aAbnw w '37 application ia ed February 18, '.969, Virginia. Polytechnic In titute (V?!) at 31acksburc, Virginia, subnitted revised Technical Specifications fer inecr;cration into Facility icense No. R-62, pursuant to Sec-icn 50 36 er 10 073 Far: 50. This revisten of the Technical Specificcticns incluces c.e addition of scetiens en definitieno and administrative require ents, ar.d the :larificatien and correction cf certain parts of the existing Technical !?;e:fi:.: dens :: nere precisel/ delineate the performance es;nbilitias and
- erati
- n cf certain reacter conpenents.
The Technical 3pecifica:icns, as revined by the applicant, include: 1. definition of key terns ased in the specifications, 2. descrip:icn cf these facility features which are in; rtant to reac cr safety, e.<.e.an..... c>.u,..~ 1 < <.. a. s_. ,../ sy.en se....s a .i.. o ...e i.. for th::a vcriables having safety significance, delinea:10n cf the liniting epnditicns for operation which define the ic.est acce;;able perfor=ance level for equipnent, e.nd the technical conditions necessary for centinued cpara:1cn. 3 requirenants for surveillance cf equipnent which 1-essential :: recetor safety, and 5. sininistra ve eww:cv;. jequired fcr facility operation. .he addition of ecti:ns on definiti:ns c41 adninistrative requirenents ani the revisiens tc :ther sections set fcr:1. the requirenants and linita-1:ns f0r rea: cr 0;erc-icn nere clearly and precisely than the existing Techni:al -a.4. s.-< c...4 m, scososo. M
[. o Ch:.3:c in tha 1in ing vnita cf C, ntu<1 = rea:tivity input rate of the uf ty ani shim r:ds, the.ini=:: reactivity shutdcun margin, and
- ..u :. ximr. 7:lca.co rate of crc:W. frc: the stack have also been in crporatei in*.c the revisei spe:ifications. The existing Tec.".nical 3 e:ifi:2 icns specify a nnximum reactivity input rate of the safety
- nd sais rei: Of 0.00 % acita k/k/seccnd and a minisus shutdcun margin cf 0.0 delta %ft. vith th:t cafety r:d Of maximu resetivity worth ard
.he regula: ins r:i fully withd cun. F.eacter measurements have chovn tha maximum reactivity input rate Of the safety and shi rods tc te in cxcess cf C.0 5 del a k/k/se:end. Aisc, a minisus shutdcun margin .-f 0. M del *,a k/k is not achievable with an excess reactivity of 0.6% deit-k/k, ta:ed en ceasred reactivity worths of the shis, safety, uni ra3uicting reds. We have evaluated reacter operation with a maxi-
- 1 r:d r: activity input rate of 0.32% delta k/k/second and a a..:
- nin= shutd vn marsin cf 0 5% del
- a k/k, as contained in the revised 2pacifications, and have fcund that operatien with these limits is c.c c-table if tha.2xtrum excess raaetivity is li=ited to C.6% delta r.....
i l
- n :ha revind :pe:ifica*.icnz, the ar. :n--i has been increases fr : 13";ucinus s' lovable release rate of c ries /see to 10 curies /see w:..h -he added licitation cf a caximum release of 315 cu-ies cf crgen.
-; p:r calenda.r year. F.casu enants at the fa:ility durips fall p:ver Op2ra,ticn ancved a gen l.i release rates.'sin excess of 1CN curies ;er l seceni. Since the existing lini Of 10 curies / cec was based on an . _ _,.... m_, yc m-.s.,,.o,4 ease, v c,,e,..a.< ..o c e..,. c....,.e.,.., u. .w. 2 c A e. .e er building chielding factors, a releace ra e of 10-' curies /see vill no: :.ffe:: the =aximum possible exposures to the general public if th inte r".ted release is limited to 315 curies per calendar year. l We have reviaved the remaining specificaticns and changes therato and have determined that the '.imits on reacter power, excess reactivity and rea:- tivi;y ver;ns Of experiments provide sufficient assurance that an e.cen-
- r
- lici r: Lease cf rs.ii: activity vill not c cur. Furthermore, it is or
- ncl.sion that the ca'ety syste: sattings and the limits en plant equip-an: p
'---<.:e and plan: technical characteristics, the specifica;icns cn surveillance cf reae:cr co=p:nents ard systems, ard the administrative
- ntr:ls will provide a:surance of afe facility operation.
M9 O 6 r
p- "\\' ,. es e e . Q- ~;.34.1 c. the 0.beve,.e cenc1;,f.e ,ht,- the ' ccrporaticn cf *.he 'ev^'- c;nn On.Sje:ifica;icns, vi-h :.:difications agreed to b7 t*.e a.P b.ed - a.. s -,,-{,-.,e - ----../,a cena.e,oes nc; invcive. significant ha:ceda consider- --..erent.rc.~ t cse previously evCusted and that tha e i-a.--... [*023 1e 3;rance that t:r.e health and safety of the public si,$ net ~~ e.....,.. e _. F V.. ..,., q,.+ . :,.., </ Ocnald J. Skovholt h,ssictant Directcr for Reactcr C; era-icn; viaica of Reactor Licensir.g Onte: breh 20, 1369 i 0 J l + s-- ,}}