ML19262C660
| ML19262C660 | |
| Person / Time | |
|---|---|
| Site: | Dresden |
| Issue date: | 02/01/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19262C661 | List: |
| References | |
| NUDOCS 8002150240 | |
| Download: ML19262C660 (12) | |
Text
I pa afog f
o, UNITED STATES y
g NUCLEAR REGULATORY COMMISSION g
-l WASHINGTON, D. C. 20555
%.... /
COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 DRESDEN STATION UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment to. 47 License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 4,1980, complies with the standards and requirements of the Atomic Energy Act cf 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B..The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be condueted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the coninon defense and security or to the health and safety of the public, and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Provisional Operating License No. DPR-19 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment fio. 47, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
80 0215 0 M
2
. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION LO. R lk}
u p Thomas A. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 1,1980
ATTACHMENT TO LICENSE AMENDMENT NO. 47 PROVISIONAL OPERATING LICENSE NO. DPR-19 DOCKET NO. 50-237 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
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aulic snebhors whos2 except n r. noted in Specification 1.
matcriel nas bean demcnstracsd by
.13b testing or operat.ng ennerience, 4
3.6.1.2 through 3.6. I.4.
analyn'.n:. to f>a '.;s opatible with th:2inspec operati q cnviyonT.ont ch211 b2 v13 2.
Prom and af ter the time that a 1n-ir. antericined to be inopesable, i n':COc t.iil.
This ciudC, but not ncCc~;32rily be 11Ltit3d to snunn, i cont.inued reactor operation is per:nicuible I
only during the succeeding 72 houac unless incpcetion or the h,jdraulic fluid,ra-th3 anubber is cooner mae< ope rad:.e or sci;voir. fluid 0:nnactionc, and !..lah2G o to connection to the pip.i,nq anQ anchor,anOS ceptaced.
focus ring header snubbers may in acCoru verify sa'abhfr ocor3011'its i:. inoper ahl.: in < oups of up to -bree O) pa i s : no t. i l :1< pt.cnt.c r 1, 1980, to f acilitate with che following cchudulo:
a l 1.o 1.n o s n.i c k I.ro t o n :opport i n..
im.
r.ii ic.iis.w.
3.
If the r.u;uirements of 3.6.1. I and No. of Snubters 1ound Next Requ.tred l. i.. t..! c.in not. be met, an orderly Inoparab)., During In-I n.:mec t ion Intitval
- butdu..n : hall ba in3t. tat.d and
.c gection Int crval C
- i. a d-r.-
. l.or
- h.i l l bo in cold
.hu' d. wn or 18 months 1 2'an M
rat ua l cond it ion within 36 houra.
0 12 months i 25%
1 4.
If a anubb"r is determined to be inoperable 6 months +- 25%
w il le-t, h. ' i e.u t or ic in the cold rhutdcwn or 2
- 25%
124 day.;,-
t :lin 1 ano.b, the nnuhber shall be mado 3,
4 62 days 1 25%
,~
i.:p t.ic. d pr ior to reac tor 5, 6, 7 go) og.:i. int.
i
- r. t.u t o p.
rh u r.quir. rent doen n<.t apetY 31 days -+ 25%
for the
_, 8 ly.anc snubberc to surun rinq gg identit ica in paragraph 3.r.1.2 above.
period The required inspection interval nhall lengthened more than one step not be g
.r..
..onbbe r t; n.ay be.nbleil to.:.3f ety related at a tinc.
systems without prior license ataendment
... i'.. h t.. 1. r. 1 provt. led th.it n revision to Table ').6,1 in incitaleil with the next licenue amende.unt request.
91b Amendment No. 41 t
h
DPR45 I.
Shock Sttppressors (Snubbers) 11.
Itecirculation Pump Flow flismatch Shubbers are designed to prevent narbst rained The !I'CI loop celectjon logic has been pipe motion uader dynan ic loads as ::iight described in the Drenden t1uclear Power occur during an carthquake or severe transient Station linits 2 and 3 FSAR, Amendments while allowing normal thernal rnotion during 7 anil 3.
For some limited lou probability startup and shutdown. 'the consequence of occi. lent s with the recirculat ton loop operating with large spec! differences, it la p<.nsible for the logic to select the urong loop for injection, for thene limited an enoperable snubber is an increase in the
-bability of structural da:aage to piping conditions the core spray itacif is adequate
. a s r-resul t of a seisnic or other event to prevent f uel ten.peraturca f ront exccedina init iating dyna nic loads.
It is therefore allouahic limits.
!!ovever, to limit the required that all hydraulic snobbers requarco to y
probability even further, a procedural pro:ect the primary coolant syste:u or any other p linitation han been placed on the allouable safety syste:n or component be operable during g var ia t ion in g; peed hetueen the r ecirculntion reactor operation.
pumps.
llecause the snubber protection is required only
't h e licensee's analyaco indicate that nhove during low probability events, a period of 3 0. ' power the loop uAlect logic could not 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements.
N be expected to innet ton at n ; peed differential In case a shutdown is required, the allowance of F
l w- -
itelou UOZ powe r the loop select logic 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> to reach a cold shutdown condition will
' g og i vould tu.t be expccted to function at a specd permit an orderly shutdown consistent with standard operat ing procedures. Since plant start up should
// dif t erent ial of 20%.
This specification p r ov !.lca a margin of $7. in pump npeed dif(creatial not conmence with knowingly defective safety rela t ed equip:nent, Specificat ion 3.6. I. l prohibi ts c,
problem could nrine.
If the reactor 10 b
a V efore startup with inoperabic snobbers.
oper.tr ing on one ptunp, the loop (;cleCc 1C4 C 4 re-analysis of the ring header design based upon 1
t, t i p s that pivap bef ore er.ahing [Ile loop aclection.
acceleration cesponse spectra derived from the original cuction header analycis report der.on traten m
that for nortaal operation plun clu:, neithe t the header h
In add!I lon, durIng ihe ntart-up of I)rcuden nor the t o r u': penotratlon; are ove -orse wd with all
<D
- la t t ? [L van lound that o flou inismntch betueun anubher= inaperable. The limitation ut a mu imum ut ther m
palin increa.a.ie out or utu pa t a n in con hi.i.o connervat the tuo neta of jet ptunpn enuned by a digterenco r*
S ince the analy is showa that the plant c.ui oporate cafel 5
in recirculation loops could oct up a vibration indefinitely with no snubbers on the ring header, the unt il a ia!rnaatch 'n aPced Of 277. Occurred. The 11:aitation on operation und utat tup wit.h tht ee inoperable pairs until September 1, 1980 in justified. Thin timo 3
10% cand 15% speed miorantch rcSt. fictions proV O.
frann in adec;uate to allow cornple t ion of Mc.t k I extern 11 a.blit lonal margin before a pump vibration structural work.
problera ut il occur.
All safety related hydraulic snuhbers are vinuilly P
"" I I"'""'IW ""4 " W M IV-I rt.t. I ert uiuance sharing roactor oporat ion The innpection will includo verification at proper with one recirculation loop out of servico orientation, adequate hydraulic flued level and ha. not been analy:cd. Ther ofo ro, sustained proper attachment of snubber to piping and neructurca.
reactor operation under such conditions is not pa r:a i t t ed.
93