ML18026B078
| ML18026B078 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  (DPR-033, DPR-052, DPR-068) |
| Issue date: | 06/25/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| DPR-33-A-101, DPR-52-A-095, DPR-68-A-068 NUDOCS 8407090152 | |
| Download: ML18026B078 (22) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROMNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
101 License No. DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 7, 1983, complies with the standards and requirements of the Atomic Energy Act of 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 Commission; 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 conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Specifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No.
DPR-33 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 101, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
84070901S2 840b25 PDR ADOCK 05000259 P
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION P~~:
Domenic B. Vassallo, Chief Operating Reactors Branch 82 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 25, 1984
ATTACHMENT TO LICENSE AMENDMENT NO. lol FACILITY OPERATING LICENSE NO.
DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
305 311 2.
The marginal lines on these pages denote the area being changed.
3.
Add the following new page:
305A
LlNI TIN'CNnlTll&s l&l MKMTlotl stntvtl~cX REOvl RCHEYTS B.
Core Monitorin being, vtthdravn any ba bypaaead on a vtthdrwn control rod
~fter the tw1 oaa~lte
~ tn the cell c~talnlne (ceca trolled by) that eoe trel rod have baaed re-ee'ved fron the reactor core.
All ether re-fwlt~t lnterlo.ke
~hall be operab1 ~.
). to.a acfurlta 1nr ~ rlock ~
4 10 4 Xafwltn lnterlocka Core Honttortn 1.
During cot'e altet'scions, except.
as in 3.10.B.2, uo SRM's shall be operable, in or adjacent to any quadrant Mhere fu>>
1 or control rods are being mov>>d.
For an SRM to be considered operable.
the following shall b>> satisfied:
a.
~
The SR.'i shall be inserted to the normal operating level.
(Use of spec ial moveabl>>,
dunking type date'tora during initial fu>>1 loading and ma)or core alteratinns in place of normal detectors is ~per-missible ns lung as th>> detecto is connected to the normal SRM circuit.)
Prior to teakinS any alteratlona to the cor ~ the AA' ahall be functionally teated and checked for neutron reaponee.
Ther ~-
after
~ vhil~ required to be
~crab le, the QH' vil1 be ahacka4 daily. far response except as specified in 3.10.B.l.b.2.
b.l The SRM shall have a
minimum. of 3 cps with all rods fully inserted in the core, if one or more fuel assemblies are in the core, or, b.2 During a full core reload where both irradiated and fresh fuel is being loaded, SRH's (FLC's) may have a
count rate of <3 cps provided that the SR."I's are respon'se checked at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with a neutron source until >3 cps can be maintained, and provided also that the core is loaded in a spiral sequence only, or 305 Amendment No.
101
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.10.B b.3 During a full core reload where both irradiated and fresh fuel are being
- loaded, four (4) irradi-ated fuel assemblies will be placed adjacent to each SRM to establish a count rate of >3 cps, provided each SRM is functionally tested prior to adjacent fuel loading, a neutron response is observed as the adjacent fuel is loaded, and the core is loaded in a spiral sequence only after the SRM adjacent fuel loading.
305A Amendment No.
101
BASES B.
REFERENCES 1.
Refueling interlocks (BFNP FSAR Subsection 7.6)
Coze Monieorin The SR>'s Rii are provided eo monitor tha core during periods of station shutdown and to guide the operator during refueling operations and station startup.
Requiring tvo oparabla SRM's in or adjacent eo any core quadrant where fuel or control rods are being moved assures ada-quaea monitoring of chat quadrant during such alterations.
The require-ment o
counts par second provides assuranca that neutron flux i.s being monitozad and ensures that seartup is conducted onl if th on y t a source accident.
g ux level is above eha minimum assumed in the contr 1
d d a con ro ro zop During a full core reload SRM/FLC (Fuel Loading Chamber) operability will be verified using a portable external source at lease once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> until sufficient fuel has been loaded to maintain 3 cps.
A large number of fuel assemblies will not be requir'ad to maintain 3 cps.
This increased surveillance race assures proper detector operabili.ty until that time.
During a full core reload, irradiated fuel may be placed adjacent to each SRM to maintain a count rate
>3 cps.
Four (4) irradiated fuel assemblies will be placed in the four adjacent fuel locations to each SRM to establish the
>3 cps count rate.
The response of each SRM to the adjacent fuel loading will demonstrate neutron response.
Each SRM will be functionally tested prior to loading the adjacent fuel 'assemblies.
This precludes the use of FLC's as mandatory for a full core reload.
Under the special condition of removing the full core with all control rods inserted and electrically disarmed, it is permissible eo allow SRN count rate to decrease below 3 cps.
All fuel moves during cora unloading will raduca rcactivi.ty.
Te is axpacead that ehe SRM's will drop belov 3 cps before all of the fuel is unloaded.
Since there will be no reactivity additions during this period, tha low'number of counts vill not present a hazard.
Whaix all of the fuel has been removed eo tha spent fuel storage
- pool, SRH's vill no longer be required.
Requiring the SRH's to be functionally tasted prior to fuel removal assures that eha SRM's will be operable at the start of fuel removal.
The daily response check of tha SRM's ensures their contin>>ad operability iineil the'count race diminislias duc to fuel removal.
Control rods in calls from which nll f>>al lies been removed and which ar<<. outside eha periphery oC eha than axiscing fuel matrix mny ba armed <<1acerically and moved foz maintcn incc purposes during full coza removal, provided all rods that control fuel are fully inserted and electrically disarmed.
REFEREiNCE,S 1,
Neutron Monitoring System (BFNP FSAR Subsaci:ion 7
~ 5) 2.
- Morgan, W. R.,"In-Cora Neutron Monitoring System for General Elactzi,c Boiling Water Reactors,"
General Electric Company, Atomic Power Equipmane Department, Novambar 1968, revised April 1969 (APED-5706)
Amendment No.~,
101 311
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()N 0 Wy*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING L'ICENSE Amendment No. 95 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 7, 1983, complies with the standards and requirements of the Atomic Energy Act of 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 Commission; 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 conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Specifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No.
DPR-52 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 95, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
k FOR THE NUCLEAR REGULATORY COMMISSION
/
Domenic B. Vassallo, Chief Operating Reactors Branch ¹2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 25, 1984
ATTACHMENT TO LICENSE AMENDMENT NO. 95 FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
305 311 2.
The marginal lines on these pages denote the area being changed.
- 3. Add the following new page:
305A
I. I Pc I T I Nc CCXInl T l(Ws M1 opKRATIoII B.
Core Mcnirorin be inc, vt t hd earn asy bo bypaa ~ ad on a vithdrwa control rod
~ ftor tha twl aoaoeabliaa in th4 call eoataialn4 (cease trollod by) chic aoo-cra i eod hava boon ro>>
aovad feon tha roaator core.
All ~thor ra-fuel I ~ g, iotarlo".ka
~hall ba oporabla.
a.
~
Thc SR.'I shall be inserted to thc normal operating level.
(Use of sperial movcnblc, dunking type detector<<dux'ing initial fuel loading and major core altcratinns in place nf noma 1 detectors is per-missible ns long as the dctecto is connected to the normal SRUTI circuit.)
1.
During core alterations, except.
as in 3.10.B.2, tvo SR'I's shall be operable, in or adjaccn to any quadrant where fuel or control rods are being moved.
For un SRH to be considered operable.
the folloving shall bc satisfied:
5IATYtlLIMCX s.EOVI RDIEYTS 4 ~ 10.4 aefualin lntarlock ~
Cora Honieorin Prior co making any al terat iona to Cha cora tha SKI's ahall be fooctionally taatad and chackcd for naueron response
Thar ~-
a!tar, vhil~ roSuirad to be
~arabia, the SXH'a vill be ahacked daily far response except as specified in 3.10.B.l.b.2.
b.l The SRM shall have a
minimum of 3 cps with all rods fully inserted in the core, if one or more fuel assemblies are in the core, or, b.2 During a full core reload where both irradiated and fresh fuel is being loaded, SRM's (FLC's) may have a
count rate of <3 cps provided that the SR."!'s are response checked at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with a neutron source until >3 cps can be maintained, and provided also that thc core is loaded in a spiral l
sequence only, or 305 Amendment No. W 95
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- 3. 10. B b.3 During a full core reload where both irradiated and fresh fuel are being
- loaded, four (4) irradi-ated fuel assemblies will be placed ad5acent to each SRM to establish a count rate of'3 cps, provided each SRM is functionally tested prior to adJacent fuel loading, a neutron response is observed as the ad5acent fuel is loaded, and the core is loaded in a spiral sequence only after the SRM ad5acent fuel loading.
Amendment No.
95 305A
BASES REPERENCES 1.
Refueling interlocks (BPNP FSAR Subsection 7.6)
Core Monitorin The S RM s are provided to monitor the core during periods of station shutdown and to guide the operator during refueling operations and core uadra station startup.'equiring two operable SRM's in or adj s
n or a jacent to any core qua rant where fuel or control rods are being moved assures ade-quate monitoring of that quadrant during such alterations.
The r<<quire-mcnt of 3 counts per second provides assurance that neutron flux is being monitored and ensures that startup is conducted only if the source range flux level is above the minimum assumed in thc control rod drop acc ent.
I During a full core reload SRM/FLC (Fuel Loading Chamber) operability will be verified using a portable external source at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> until sufficient fuel has been loaded to maintain 3 cps.
A large number of fuel assemblies will not be required to maintain 3 cps.
This increased surveillance rate assures proper detector operability until that time.
During a full core reload, irradiated fuel may be placed adjacent to each SRM to maintain a count rate )3 cps.
Four (4) irradiated fuel assemblies will be placed in the four adjacent fuel locations to each SHM to establish the )3 cps count rate.
The response of each SHM to the adjacent fuel loading will demonstrate neutron response.
Each SRM will be functionally tested prior to loading the adjacent fuel assemblies.
This precludes the use of FLC's as mandatory for a full core reload.
Under the special condition of removing the full core with all control rods inserted and electrically disarmed, it is permissible to allow SRM count rate to decrease belo~
3 cps.
All fuel moves during core unloading will re<luce reactivity.
'It is expected that the SRM's will drop below 3 cps b<<fore all of the fuel is unloaded.
Since there will be no reactivity additions during this period, the low number of counts will not present a hazard.
Whcii all of thc fuel has been removed to the sp<<nt fuel storage
- pool, SRM's will no longer be required.
Requiring the SRM's to be functionally tested prior to fuel removal assures that the SRM's vill be operable at the start of fuel removal.
The daily response check of the SRM's ensures their cantiniicd operability until the'count rate dindnishcs due to fuel removal.
Ciintrol rods in cells from which al] fuel has been removed and which are outside thc periphery of the then existing fuel matrix may bc armed <<1<<ctrically and moved for maintcn Ance purposes during full core removal, provided all rods that control. fuel are fully inserted and electrically disarmed.
REFERENCES 1,
Neutron Moilltoling System (BFNP FSAR Siibscction 7
~ 5) 2.
- Morgan, W. R., "In-Core Neutron Monitoring System for Ccneral Electric Boiling Water Reactors,"
Cn.neral Elcctri.c Company, Atomic Power Equipmcnt Department, November 1968, revised April 1969 (APED-5706)
Amendment No. Pf, 95 311
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l UNITED STATES NUCLEAR REGULATORY COMMISSiON WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCL'EAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No 68 License No.
DPR-68 1.
The Nuclear Regulatory Commission (the Commission)'as found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 7, 1983, complies with the standards and requirements of the Atomic Energy Act of 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 Commission; 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 conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Specifications as indicated in the attachment to this'icense amendment and paragraph 2.C(2) of Facility Operating License No.
DPR-68 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 68, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
+yzP~rt~e Domenic B. Vassallo, Chief Operating Reactors Branch t2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 25, 1984
ATTACHMENT TO LICENSE AMENDMENT.NO. 68 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise Appendix A as fol 1 ows:
1.
Remove the following pages and replace with identically numbered pages.
336 342 2.
The marginal lines on these pages denote the area being changed.
3.
Add the following new page:
336A
l )> ) ) >><<'0><>>) 1 loss
/OA
~
ANATlos 5QXVtIi.)~CX ))
(.<)I(l AI.'I'l.lU'I' ()>)!>
~>. I <)
I:<)!II Al.'I'I>IIVl'l<)l'!>
Co>
~>nn> korin b ~
Cora Honltori<>
1.
>)iiri>>); e<irc;>1terat)uns, except
~ l.>
I i>
3 ~ I I) ~ I) ~
Lwo Sl(>>'i
'.<> 1 I b>." >>p<r;>I>l<~,
in or a<lj:i<<>>L
).<> any
<1<<a>lr:>>i<
vii< re fi>el or co>>L'rul i <><Is;>r>
I>< ~ inv, m<>v<<<i.
I'>>r:>>> SIIH
(<>
I><:
> <'i I <><'r <<'
<>p<'rob I >> >
I><.',>l lo<rinn>>li.>11 be
~.>L is! icd:
Prior ro +akin>L any alterationo to tha coia Lh>> SRN' ohail be fuoctio<>ally teated and checked lor nau<ron response.
Thara-altar, vhil ~ required to be
~
o)>arabia, tha
<<'>>8' vill be checked daily !or taaponaa except as specified in 3>10.B.l.b.2.
a
~
I'I>c SIQI slia I 1 bc i>>s<!rr:cd to
< li<~
>>'ria I <era r l I>)',
I ('vol.
(l)sc o) sp> <'>> I
>l><>v< i>l> ~ >
~
>l<<>>kiri);
! yl>c <loL> cL ~>rs <liiring i '> i )'
>1 I I I><, I 10)i); rlil<l rei j<>>'ore al LeraL ioiis i>> place
<>f
>1<>l r>~ > I <I<'.I.e<'ors i s p<'r-niasil>le;is l<<ii)',.is I li(
<I< r(ctoi is <<<>i>>i>>>ted Lo tlic>><>rmai SINAI
<' <ii > i, )
b.l Tl>;i 1 I I>:iv<
.i mlniniim uf I
> )>s
> ~ i L>
~e <'>>rc, if unc
<>r n>>i'> f<<cl ass<<mlilies
>>re in Lli<<<:orc, or b.Z During a full core reload where both irradiated and fresh fuel is being loaded, SR"I's (Fl.C's) may have a
count rate of <3 cps provided chat the SRai's are response checked at 'east once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Mich a neutron source until >3 cps can be maintained,
.ind
'rovided also thar.
rhe core is loaded in a spiral sequence only or 3'll>
Amendment No. 68
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- 3. 10. B.
b.3 During a full core reload where both 'rad'ted and fresh.uel are being
- loaded, four (4) irradi-ated fuel assemblies will bc placed adjacent to each SBM to establish a count rate of >3 cps, provided each SRH is functionally tested prior to aajacent fuel loading, a neutron response is observed as the adjacent
. uel s loaded, and the cor e is 'oaded in a spiral sequence only after ti;e SFH adjacent fuel lcadirg.
336A Amendment No. 68
)s<'<>v> l>>'>< I<<> >< y
~ 'c><:<,
< v a
< y
<:\\><<< r<>!
t <>a tl>>'
>>>'l
><<>)<'mt>li <'<<
<>>e ~ ci l!
~><<><<><: Ln > <<<! wit t> t l>a<. co>>taol a'o<l Tt>>><>,
~ >n<>v.> I n t
.><<>!<><. a r> ~ <:el l (t uel ns>><mt>la ~:s t>lu>> cont rol
<<> It t> ~ <<> a<<>
i <>
i>
l<><<>>r react avi ty po<<'nti >L ot tt><.'ore.
Tt><<r <!<tua <<m<<'>ts !or '>ltd oper.>bility 8ur inq these core al terat ions assure sutf fc!.ent core mo!>itor!.nq.
~
~
Refu L;nq ant crlocxs
[BF'.tp FS> R Subsection
- 7. t'>1 B.
Co r e Hon ito r~xr.
Tt!e St)M ~ s are provaded to monitor the core durinq period-of station shutdown,!<>d to quide the ol>erator duri)>q rcfuelinq nt>crations and "tation star cup.
Requiri<aq two operable SRH>s in or ad jac<!nt to>>ny core quadra<at where fuel or co)>t:rol r<!<tu ar b>>is><t moved assures a>dc<<uat n monitor inq of that qu,><ira<<t dur ar>q suet>
a l terat iona.
The requicem<!nt of 3
count s;>~r
.".<!cond>>rov iJ>!s as::uranc<! that
>>eutan<> flux is b< i<><! m<><>itor<<l n<>l insures tl>at tartup an co)><lucted only if tl><'o<>r<!<'.>cue
- t. lux level iu abov<! the minimum assumed in the control rod drop accident.
During a full core reload SRM/FLC (Fuel Loading Chamber) operabil'ty will be verified using a portable external source at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> until sufficient fuel has been loaded to maintain 3 cps.
A large number of fuel assemblies will not be requ'red to maintain 3 cps.
This increased surveillance rate assures proper detector operability until that time.
During a full core reload, irradiated fuel may be placed adjacent to each SRM to maintain a count rate
>3 cps.
Four (4) irradiated fuel assemblies will be placed in the four adjacent fuel locations to each SRM to establish the
>3 cps count rate.
The response of each SRM to the adjacent fuel loading will demonstrate neutron response.
Each SRM will be functionally tested prior to loading the adjacent fuel assemblies.
This pr ecludes the use of FLC<s as mandatory for a full core reload.
Un<lrr t.l><. special condition of removing the full cora with all cnntrol
><"I; inserted and ele'ttrical!y disarmed, it is permissible to allow SR.t cc>::>t rata to <tccrcasc below 3 cps.
<>>LL fueL -..ovts da:ring core a):>loading will reduce reactiv'ty.
It is expected that tl>c SR."I's wil'I dr"p below 3 cps before all ci the fuel is unloaded.
Since there will be no react iv!ty additions during this pericd, the low n>>mbcr o! ccunts'will not t>r!sent a hazard.
ll><'n all of hc f><<.I I>.>.'.
b<
"-<>vcd tc (I><<
'..P ')>t f >c 1 st-r..".c;>> Ol 'R:I's will "..c longer l>c r<
~',u>:i' !.
Hc<tuiri>:g !!.! '!CI to bc functionally tcstc<l prior tn fuci cc."cvai assures:hat t.".c S."'t's <<ail bc cperablc at the s.ar! of fuel rc:;<>val.
1t>c <taiiy rcspa<!sc ch<.'ci'f thc SR>l a ensures tl>cir r< ntin<<c<E operability un(.xl th c ant rate diminishes cue to fuel r(mnval.
t onr rol rods in tel I s f.-om
< h! cl> a.'
fuc I has been r(Plo"c<i Il'ay bv ll<-.c<t c) era r ica i I y and mo:c<t far ma int >>an.c purp" ses d >ri<>S f<<l I core rc<"ov.>.', pr<>v.dcd al'ods that control fuel are fully i>>sorted and clcctrically dasarmed.
Amendment No., 68 342