Proposed Tech Spec Changes 1.1-3.2.3 to Permit Reactor Power Ascension to Proceed Along Modified Power/Flow Line,For Dresden Facility| ML17174A105 |
| Person / Time |
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| Site: |
Dresden  |
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| Issue date: |
11/01/1979 |
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| From: |
COMMONWEALTH EDISON CO. |
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| To: |
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| Shared Package |
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| ML17174A103 |
List: |
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| References |
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| NUDOCS 7911060334 |
| Download: ML17174A105 (6) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20199E0361999-01-12012 January 1999
Proposed Tech Specs Section 3.10, Fuel Handling & Storage, Eliminating Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS
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ML17187A7991997-02-17017 February 1997
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ML20135B0581996-11-25025 November 1996
Proposed Tech Specs,Submitting Update to Administrative Controls Section of TS Which Reflects Transition of Overall Corporate Responsibility for Storage of Spent Nuclear Fuel
ML20129F3231996-10-23023 October 1996
Proposed Tech Specs Replacing All Existing Pages of Unit 1 TS
ML20129C2391996-10-16016 October 1996
Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage
ML20129D3981996-09-20020 September 1996
Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases
ML20113B6001996-06-20020 June 1996
Proposed Tech Specs,Incorporating New NRC Approved Thermal Limit Licensing Methodology in List of Approved Methodologies Used in Establishing Thermal Limits in Cycle Specific COLR & Change to Fuel Assembly Design Features
ML20112E6341996-05-22022 May 1996
Proposed Tech Specs Requesting Emergency Amend to License DPR-25 Temporarily Modifying Description of Certain Corner Room Steel Supports to Match Current Configuration Until Mod During Next Refueling Outage
ML20086D4741995-06-30030 June 1995
Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2
ML20087H8651995-05-0202 May 1995
Proposed Tech Specs Re TS Upgrade Program Section 3/4.10
ML20125D6381992-12-0808 December 1992
Proposed Tech Specs 3/4.1 Re Reactor Protection Sys
ML20106A6221992-09-15015 September 1992
Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits
ML20099D7791992-07-29029 July 1992
Proposed Tech Specs Sections 1.0, Definitions, 3/4.0, Applicability & 3/4.3, Reactivity
ML20096F1161992-04-24024 April 1992
Proposed Ts,Changing OL Section 2.G Re Reporting Requirements
ML20058L9381990-07-31031 July 1990
Proposed Tech Specs Reflecting Nonoperating Status of Facility & Clarifying Section 3.10.F
ML20137C2401986-01-0707 January 1986
Proposed Tech Specs,Deleting Authority to Operate Unit & Sys Requirements & Surveillances No Longer Applicable
ML20052C0761982-04-29029 April 1982
Proposed Changes to Licenses DPR-19,DPR-25,DPR-29 & DPR-30 Re Surveillance Requirements to Test Automatic Pressure Relief Valves Daily When HPCI Subsystem Is Inoperable
ML17194A4181982-01-12012 January 1982
Revised Tech Spec Tables 4.2.1 & 3.2.4 Re Restoring Inoperable Indication Prior to Startup
ML17194A4061982-01-11011 January 1982
Proposed Tech Specs Re Reload Fuel & Core Design,Transients & Accident Analyses & LOCA Analysis
ML18025B6791981-10-19019 October 1981
Proposed Revisions to Tech Spec 4.7.A Re Surveillance Requirements,Primary Containment
ML19343D1181981-04-0303 April 1981
Proposed Revision to Tech Spec Table 3.6.1
ML19309H8901980-05-15015 May 1980
Proposed Changes to Tech Specs,Deleting Requirement to Maintain at Least Three Counts Per Second on Each Source Range Monitor When Only Two Fuel Assemblies Are in Quadrant
ML17174A1051979-11-0101 November 1979
Proposed Tech Spec Changes 1.1-3.2.3 to Permit Reactor Power Ascension to Proceed Along Modified Power/Flow Line,For Dresden Facility
ML17174A1061979-11-0101 November 1979
Proposed Tech Spec Changes 1.1-3.2.3 to Permit Reactor Power Ascension to Proceed Along Modified Power/Flow Line,For Dresden Facility
ML17174A1071979-11-0101 November 1979
Proposed Tech Spec Changes 1.1-3.2.3.,for Quad-Cities Facility
ML17174A1081979-11-0101 November 1979
Proposed Tech Spec Changes 1.1-3.2.3.,for Quad-Cities Facility
ML20084D2751974-01-30030 January 1974
Proposed Tech Spec 15.4.11 Re Hydraulic Shock Suppressors
1999-01-12
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
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Revs to Odcm,Including Rev 2.0 to Chapter 10, Radioactive Effluent Treatment & Monitoring & Rev 1.9 to Chapter 12, Radiological Effluent Technical Stds (Rets)
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Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document
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Qualified Unit 1 Supervisor Initial & Continuing Training Program
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Rev 1.8 to Chapter 12 of Dresden Station Odcm
ML20217N9331998-04-30030 April 1998
Rev 1.7 to Chapter 12 of Dresden Station Odcm
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Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F
ML20216H8551997-12-31031 December 1997
Revs to OCDM for Dresden Station,Including Rev 1.9 to Chapter 10,rev 1.3 to Chapter 11,rev 1.6 to Chapter 12 & Rev 1.1 to App F
ML20198M2491997-12-18018 December 1997
Revs to Ocdm,Including Rev 1.3 to Chapter 11, Radiologicial Environ Monitoring Program & Rev 1.6 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20216H8241997-10-31031 October 1997
Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F
ML20216H9041997-10-31031 October 1997
Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F
ML20198P1601997-10-20020 October 1997
Rev 1.5 to Odcm,Chapter 12
ML20212A2941997-10-0202 October 1997
Rev 56 to Dresden Nuclear Power Plant for Insertion in NRC Security Plan.Rev Withheld
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Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates
ML20196G8781997-07-18018 July 1997
Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program
ML20148K6141997-06-0505 June 1997
Proposed Tech Specs,Updating Revised TS to Format Consistent W/Recently Approved TS Upgrade for DNP & Proposed Other Miscellaneous Changes Re Decommissioning Status of Unit 1
ML20141A6411997-05-31031 May 1997
Rev 1.4,Chapter 12 to Radiological Effluent Technical Stds (RETS) of ODCM
ML20216H8691997-03-31031 March 1997
Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F
ML17187A7991997-02-17017 February 1997
Proposed Tech Specs 3/4.7.K & 3/4.8.C Re Issues Resulting from Comeds Efforts to Reconstitute Design Basis of Chrs
ML20137C0011997-01-31031 January 1997
Odcm,Dresden Annex Revs 1.9 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.2 to Chapter 11, Radiological Environ Monitoring Program & 1.3 to Chapter 12, Radiological Effluent Technical Standards
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Proposed Tech Specs,Submitting Update to Administrative Controls Section of TS Which Reflects Transition of Overall Corporate Responsibility for Storage of Spent Nuclear Fuel
ML20129F3231996-10-23023 October 1996
Proposed Tech Specs Replacing All Existing Pages of Unit 1 TS
ML20129C2391996-10-16016 October 1996
Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage
ML20129D3981996-09-20020 September 1996
Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases
ML20216H8841996-06-30030 June 1996
Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F
ML20113B6001996-06-20020 June 1996
Proposed Tech Specs,Incorporating New NRC Approved Thermal Limit Licensing Methodology in List of Approved Methodologies Used in Establishing Thermal Limits in Cycle Specific COLR & Change to Fuel Assembly Design Features
ML20112E6341996-05-22022 May 1996
Proposed Tech Specs Requesting Emergency Amend to License DPR-25 Temporarily Modifying Description of Certain Corner Room Steel Supports to Match Current Configuration Until Mod During Next Refueling Outage
ML20086D4741995-06-30030 June 1995
Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2
ML20092C8091995-05-12012 May 1995
Rev 2, Shroud Repairs Program for Dresden Units 2 & 3, Back-up Calculations for RPV Stress Rept Number 25A5691, May 1995
ML20087H8651995-05-0202 May 1995
Proposed Tech Specs Re TS Upgrade Program Section 3/4.10
ML20085M6171994-07-31031 July 1994
Rev 1.1 to Chapter 12, Radioactive Effluent Technical Stds of Dresden ODCM
ML20063F9011994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Dresden Station Units 2 & 3
ML17179B0931993-09-10010 September 1993
Rev 2 to Dresden Station 3rd Interval IST Plan, Sections 2,13 & 14,pages 2-1,13-1 to 13-4 & 14-40,respectively
ML20058E8751993-09-0303 September 1993
Revised AOP-6.3, Loss of RHR Shutdown Cooling
ML20058E8351993-06-10010 June 1993
Revised AOP-7.4, Control Room Inaccessibility
ML20127D0691992-12-30030 December 1992
Corporate Emergency Response Organization Required Reading Package 92-11
ML20125D6381992-12-0808 December 1992
Proposed Tech Specs 3/4.1 Re Reactor Protection Sys
ML20058E8681992-09-29029 September 1992
Rev 56A to AOP 1BOA PRI-5, Control Room Inaccessibility Unit 1
ML20106A6221992-09-15015 September 1992
Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits
ML20081M1251992-08-31031 August 1992
Rev 17 to Procedure Dgp 03-04 Control Rod Movements
ML20099D7791992-07-29029 July 1992
Proposed Tech Specs Sections 1.0, Definitions, 3/4.0, Applicability & 3/4.3, Reactivity
ML20096F1161992-04-24024 April 1992
Proposed Ts,Changing OL Section 2.G Re Reporting Requirements
ML20081M1851992-01-31031 January 1992
Rev 17 to Procedure DAP 07-02, Conduct of Shift Operations
ML20081M1611991-11-20020 November 1991
Rev 0 to Procedure DAP 14-4, Control Rod Sequences
ML20058E8761991-11-18018 November 1991
Rev 56 to AOP Bwoa PRI-10, Loss of Rh Cooling Unit 1
ML20081M0311991-11-15015 November 1991
Rev 2 to Procedure Doa 0300-12, Mispositioned Control Rod (W-2,W-3)
ML20081M1721991-08-31031 August 1991
Rev 15 to Procedure DAP 07-01, Operations Dept Organization
ML20081M1401991-05-17017 May 1991
Rev 6 to Procedure DOP 0400-02, Control Rod Minimizer
ML20081M1971990-08-30030 August 1990
Rev 9 to Procedure DAP 07-05, Operating Logs & Records
1999-04-30
[Table view] |
Text
ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGES FOR DRESDEN 2 s ..
,r-'\.
\ }
DPR-19 1.1 SAFETY LIMIT 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
.w 0
~ settinq in percent of rated power
=percent of drive flow required to produce a rated core flow of 98.
Mlb/hr. .
I 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.
6
.. ************** ****** _, ........... ___ ..... -----**-*- .. **-*-* .... -*- -*-* --* -- -- -- ***-. ~*
DPR-19 1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING .,
Core Thermal Power Limit (Reactor B.
Pressure = 800 psig) 3.
- IRM Flux Scram Trip Setting When the reactor pressure is ~eoo psig The IRM flux scram setting shall be or core flow. is less than 10% of rated, set at less than or equal to 120/125 the core* thermal power shall not exceed of full scale.
25% of rated thermal power.
- c. Power Transient B~ APRM Rod Block Setting
- 1. The neutron flux shall not exceed the scram setting established in Specif ica- The APRM rod block setting shall be:
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 SL f~o*sawD sol-1 . fi.TPF]
+
\2'PF service, this safety limit shall be assumed to be exceeded if the neutron The definitions u~ed above for the APRM flux'exceeds the scram settin<J scram trip apply. .
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) 7
DPR-19 ROD BLOCK APRM BACKUP SCRAM INTERCEPT LINE
.. .:..:.... - - - . -,- - -r--
/
100
/
t.PR~ SCRA~
'\ //
l IN[ (0. '.;jf:.-.'i) 62)
' 'v/ ..;.
D /
w
a: eo - /
L... I 0
/ ,'*
~
I a:
w 3
0-Q. N!):.11 Nl\I, ( 0:-1:,J l\NI XI l*!ON c_ 1;~C\Jl .*'\ l lljN
- _..J ;(li.J/100 l'()-.<<i.ll/f-l.C:l'I LINE
< LI r.:E
~
n: E*O -
.r:
w er 0
u I 40 -
Oi'lf1Al1NG RIGION SUl'i'Oi-ll D II BY N.r.n 0. - 24167 Op:*rating on Single Loop I or Natural* Circuletion is I.imi.ted per Tech Specs.
I } .__fi:_ :J. and _3_: 0-~-* ~
II Ji/, I I U ( ( ':!' l I l I\ H~'.-,
l'(l\.J.l'l-1 I I
< <111r: ri. m.
I c -*-*
L?O II 0 :;o ..:o e.o 100 I
I
\.Jl' CORI I J O\.J Ji Al[ er UI 111. l I 0)
I ,.,_l-.lH~r ?.1-3
('...CHIY..:.l 1C) l ;.1 *;.;M I l (l,.,' nI /. '.:. :-.c Ii:.~ I~ r I. t l Io: :'.-.HI p 1 o ::'.Y-.1-11.~ 0;*11,:.11 r:~. co::D 111 o~:s I 18.B
- ****~-----~-:**.-***r.~T""!~~~ .............. ...,..;..~..,._....,_.. ................................_ _ _ _ _ _ __,__ _ _ _ _ _~-~~-,---------------
DPR-19 ll(SA'F..O~'"l'AT!~i~ 'IF.:\T I~!ITL'\".L-l:S ~C!> ~L~< ._ '-~
TC!lble 3.2.3
~~:::-i'.!>l~ In:tt.
cr..~~:;~ls Pc=
~::-!.*> 5,.,*::t~(l)
- I:1str._:=cr.t Tri-:> t.~vel S-"'~~i~~
.-::..::..:;;...;...r_.:;..o..;=-=-..=..;...;;..:..:::..:-4---~-?-:---.:-*:JJ-__ -~.:-::-:.-c-a-1-~-:;;..;cr-:;;.*,. .; ;._.;: ;. , . ;: ;. ;.;.b;.; i; ;.c:o;.,=-:::...>--
- . (-7-,---------~, L-
- r=--,_,;;.;;;_ * ** '.1 ** Lrwwm:.
1-L:0.5Sw0 + SOJ ~ ( 2)
TPF
.. 1 II ~ 12/125 *.fUil. scale I
2
- 1* 2 J/12; ~full .scale bi~s} (7l ;- ~ o.65Wo 1
l Red blo:i<.
~o~ bloc~ ~onito~ tlO-*-:l:iC~le
(!l-:>w (7)
+ 42 ( 2)
I
3 3 ~103/125 full.sc~l~
.. 3 IR?! cfot~cto~ not fulJ.}* in3~rted in t~c co::-~
2(5) SP.n cli:?tcctor not in nto.rt:\:p po::.H:io:i (4) 7.(5 (6
\*
DPR-19* '-
TA3~~ 3.2.3 (c6ht)
- 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 :;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 4
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
- r.rb*r S J~'1,.l *-~ .l _,......, . . _
jlt._.~l1...;.
-r. .:-~ . . ,..... (:!-r:'&..
J.J.. \...If- .... ;.,).~I-col\"'T"-. r""**
U***l -l-~J
... *-1*- *f"""\c
--i.rii.'*
.....,,,'- 17 0 ~- I"'\~-, or.~
llo*".t.,....L .... ;.:.. .. .L
'-r1_ '-'*'*0 t - '
.t..l.? ...
5~~5\,.'2~5,
.. hi .... 'co:idi:-;:cn* n'"'v 0*.-;,,.t r.or J.. t:.:J
!. '*o ...... ,.**r'n *]**....-~ n . . . c,,icc*'-'1 ..'-.I'.(..~
._...:>'-"'~--'*.I--**, __
-..,.,. ..* c~, ... l.* .... a -!'-~*""'" t;~c
...... ,a..*'-.~*~~'-*'-'*'
t"~e 9
\.. .:J .. \... .... ' J(.l.J _ ... _._.
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 .
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.
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 6;.
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}.