ML17174A105
| ML17174A105 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/01/1979 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML17174A103 | List: |
| References | |
| NUDOCS 7911060334 | |
| Download: ML17174A105 (6) | |
Text
- .
ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGES FOR DRESDEN 2 s..
1.1 SAFETY LIMIT 6
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DPR-19 2.1 L:IMITING SAFETY SYS'l'EM SETTING
- 1.
APRM Flux Scram Trip Setting (Run Mode)
When the reactor mode switch is in the run position, the APRM flux scram settinq shall be:
S '= ~.SBW0 + 61 ~~;F]
with a maxium set potnt of 120% for core
' flow equal to 98 x 10 lb/hr and greater.
where:
S ~ settinq in percent of rated power
.w0 =percent of drive flow required to I produce a rated core flow of 98.
Mlb/hr.
TPF -
LTPF un1ess the combination of power and peak LHGR is above the curve in Figure 2.1-2 at which point the actual peakinq factor value shall be used.
LTPF = 3.05 (7x7 fuel assemblies) 3.01 (8x8 fuel assemblies) 2.98 (8x8 R fuel assemblies)
- 2.
APRM Flux Scram Trip Setting (Refuel or Startup and Hot Standby Mode)
When the reactor mode switch is in the refuel or startup/hot standby position, the APRM scram shall be set at less than or equal to.15% of rated neutron flux.
_,........... ___..... -----**-*-.. **-*-*.... -*--*-* --* ------***-. ~*
DPR-19 1.1 SAFETY LIMIT B.
Core Thermal Power Limit (Reactor Pressure =
800 psig)
When the reactor pressure is ~eoo psig or core flow. is less than 10% of rated, the core* thermal power shall not exceed 25% of rated thermal power.
- c.
Power Transient
- 1. The neutron flux shall not exceed the scram setting established in Specif ica-tion 2.1.A for lon<Jer than*1.s seconds as indicated by the process canpute~.
- 2. When the process ~omputer is out of service, this safety limit shall be assumed to be exceeded if the neutron flux'exceeds the scram settin<J established by Specification 2.1.A and a control rod scram does not occur.
- o. Reactor Water Level (Shutdown Condition)
Whenever the reactor is in the shutdown condition with irradiated fuel in the reactor vessel, the water level shall not be less than that correspondinq to 12 inches above the top of the active fuel when it is seated in the core.*
- Top of active fuel is defined to be 360" above vessel zero.
(see Bases 3.2) 2.1 LIMITING SAFETY SYSTEM SETTING
- 3.
- IRM Flux Scram Trip Setting The IRM flux scram setting shall be set at less than or equal to 120/125 of full scale.
B~
APRM Rod Block Setting The APRM rod block setting shall be:
SL f o saw
+ sol. fi.TPF]
~
- D
-1 \\2'PF The definitions u~ed above for the APRM scram trip apply..
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- Op:*rating on Single Loop or Natural* Circuletion is I.imi.ted per Tech Specs.
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DPR-19 ll(SA'F..O~'"l'AT!~i~ 'IF.:\\T I~!ITL'\\".L-l:S ~C!> ~L~<
TC!lble 3.2.3
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- I:1str._:=cr.t Tri-:> t.~vel S-"'~~i~~
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TPF
~ 12/125 *.fUil. scale I I Red blo:i<.
1
- 2 J/12; ~full.scale
(!l-:>w bi~s} (7l ;- ~
o.65Wo + 42
~o~ bloc~ ~onito~ tlO-*-:l:iC~le (7)
IR?! cfot~cto~ not fulJ.}* in3~rted in t~c co::-~
SP.n cli:?tcctor not in nto.rt:\\:p po::.H:io:i
- > 5/125 !-::1:!.
~cal-:? *
~103/125 full.sc~l~
(4)
( 2)
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TA3~~ 3.2.3 (c6ht)
DPR-19*
- t::otc5:
- 1.
For the St<?.rtl.:p/~ot St<:tndby a:ld Run po~itio:lz of tho F.eactor W~C!e Selector Switch.*
therc 4 :;h~~-1 be tv.:o cp':'!runic or t::::-:..ppc:c\\ t::-i? ~y:::;'.::c~3 f~r c;;a.ch fu:-.ctior.; c:::*:ccpt t~c Si:..'~ r.od bloc!~s, IP..M tlp5c<:ll~, IR:*1 ciown:.:c;.tl.:? ar,d l?J*i d~t~ct-:>r r.o~ ful~y ir.s~::::-tcd in t!:~ co;::-c n~~ci not. b~ opcrublc i'1 th0 "r~*.lT!." po::;i'd.0:1 u:icl id~~1 C:o*.-msculc,.i\\??.:*1 upscale (flow bias), RBt.f *upscule, and RBI-I downscale need not be operable in the Startup/Hot S J ** r.rb*r _,......,... _
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opcr~hle sys te:-a is fl.i;-i(: tio:1<:llly tcs'<.:ccl irr.:71(!Uic). t.c ~y ci.~:1 d~i ly th~rc~£tcr; if this
. 9 co::C.i t. ic;1 la 5tz lons'2:::-
th.~n ~c*.-c:l d;::y:; the ~ys ~cD s'hull b~ tr ip9sd.
If the fir.st colu:r.:1 c.'.ln;1ot be m~'.: for both trip ~y*~tc::i::;~
th~ sy:;tc:ns shull :Oc t:ripp\\!ci.
Wo
- perci?nt nf drive flO:*; req:..i1red to produce a r<!ted core flow of 98 Mlbuihr*.
- 3.
!~1 down~cole m~y be bypassed when it is on its lowest r~nge.
- 4.
This function may be bypass.~d *.when th~ cc'.lnt rat~ is ~100 cps.
S.
One cf the fo*..ir* S?,H. inputs r.iu.y be oyp:lsscci.
6;.
This SP""'1
.functio:1*ma:-r~ be *byp<l:;scd in t;1c higher IRH =~ns-es,,.,.hen the IR.L'1 u?scale red block is opcrub!.~.
e
- 7.
Not requirc::d v/hile perfonning low pow~r physics tests at utmosphcr.ic pressure during or after rcfucli~g at power levels n6t to cxc~~d 5 ~~1{t}.