Proposed Tech Spec Changes 1.1-3.2.3 to Permit Reactor Power Ascension to Proceed Along Modified Power/Flow Line,For Dresden Facility| ML17174A106 |
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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 7911060359 |
| Download: ML17174A106 (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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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
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
ML20205A0871999-03-22022 March 1999
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 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
ML20196F6451998-11-30030 November 1998
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
ML20237A8651998-08-0707 August 1998
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
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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
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
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 2 PROPOSED TECHNICAL SPECIFICATION CHANGES FOR DRESDEN 3
(~-)
i-y .. ' . . .
DPR...,25 1.1 SAFErY LIHIT 2.1 LIMITING SAFETY SYSTEM SE'ITING
- 1. APR:1 Fl'JX Scra.n Tr1 u Settiniz {nun :~<Y.!c)
\..'hen the rcnctor mode switch is in the run position, the APR!i flux scram setting shall bci S ~ fa. 58Wo + 6;1 . fi,TPFl L ] LTPFJ
- vi th ~ m<J.Ximum sc t poi.n t of 120%
- fo.r core nov equal to 9a )( 10 6 lb/hr and gt'cater.
'Wheres S
- setting in per cent of rated power
-= percent of drive flow required to pro-duce a rated core flow of 98 Mlb/hr.
I TPF
- LTPF-unless the ~o~b1nat1on of power and peak LHGR is above th~ curve 1n Fieurc 2.1-2 c.t w!i:!.ch po1.:1t the actual J>e~~in~ factor value shall be used.
LTFF 0 3.05(7X7 fuel assemblies)
- 3. 01 (8X8. fuel assemblies)
- 2. *~
""J F 1.... *"'
........,.. sc~'.:t
.....~ .. ,,.,..i"D
- ... Sc 1i..*.L1-~
... "R (R,.1-uel
\iJ. or Sti.rtu;, ~.~rl. Hot Standby Mcxh? 2.
~.;;,,~!' t!1~ rc<ictot r:io~k S'-ri tch is in tile re.!'\:cl oi* Stilrt:1p/h1it st:io<lby posi-tion, the ~pj>J', sc rn;;i sh~ 11 be :;ct at lc~;s* t!10.n or equal to lSI of rnted neutron
o* . *.. ..-"
. I r-*..
\._ n ' . 0 DPR-25 1.1 .SAFE.TY Lntrr 2.1 LIMITING SAFSr? SYSTEM SEl'TING.
B. Core Th~rmal Po~"cr Limit* (Reactor Pr~~surc ~ 000 n~i~)
- 3. IRM Flux Scrnm Trt "O Setting
'file u.:*t flu~ scr~m sr.ttin3 shall be 1~cn the rc~ctor prc~surc is < BOO *set .:it *1ess th.:in or cqu.:il tQ 120/125' of psi& or core f 1011 is less thnn lOi. full scale.
of r~tcd, the ~ore thermal power shall not exceed 25 percenc 0£ rated*
the:-mc.l po:.:er.
C. ro*.1er Tr:ln!>icnt The APIU: rod block $<.:ttinc shall be:
- 1. n1c neutron flux sh~ll not exceed the scrno setting established in Specification 2.1.A s ~ [ o.saw + so]
for longer th:m l.S seconds ns indicated by 0
the process computer.
The definitions used nbove for the APR."! scr.l!:I
- 2. \.rneo the process coc?uter is out of service, trip-.:ip:-ily.
thls :;afccy limit shall be assuocd to be c:i:c~cd~d if the neutron flux e:r:cce<ls the sora::i *
- s<?.ttine cstnblishcd by Specification 2.1.A and a control rod scram docs not occur. .
D.. R~act.or V.a ter Level (Shutdo~n Condition)
\.11c:ic,,-cr the. re<Jctor is in the shutdO"..tn condition
- vit:i irr~*Jiate<l fu~l in the reactor vessel, the
.v.1.ti:?r lc.vcl shall not be less thon that corrcs-.
p0ri<lin3 to 12 inchcc .-i!>ovc the top of the active f11!.!.l v!le.n it is :;c;1tcd in the cor.c.
7
DPR-25 ROD BLOCK APRM BACKUP SCRAM INT£ RCEPT LINE
/
ROD BLOCK lh IE HCEPT 100 POINT l!!~i61) - *
/
/
-~///
APRM SCRAM l I N[ (0 . 'j81-!J" 62 )
0 w ,. /
I- /
<l cr eo /
I.... I
j
~
I er w I 3
0
- n.
- r.;.t.. *i ur-~,~L ClilCUl ,\ 1 iON 1::;~.~I Nfll., ( (')~"'." t.NT xruON
_J LINE - 10J/10J ;-(;':*U'fc l 01'1 LINE er (,Q -
w I
w er 0
u 40 --
- --***---- r:-~ Oil li A I 1 IJC f.< IC I ON ~.UI ., :;Ji< I D r-=:::-.J l;Y N. r. D 0. - ;*!11 G7
- Opc*;*atj n& on ;,i ngJ e Lo0p
\Ir N..-,_ti1rnl Ci1*cul<iti0n is LirnitccJ per '.1\'ch. :3p<'c:s;
'.\. (~J!. 3 ;*nil '< J;I\ .11 ru.11 o couoi i 10NS I '\!~.'LR r Ort [ I LOW
. 0 --*-- .. -
0 ~o 40
'----***** 100
\.JI* (Oiif rlO\..' RAH (;f 01 fhllD) r , c;\1;1 r 2. 1 - 3
( '.( 11[ l'.f. I IC)
/,l'i'1*1 11 (I..' 1111.~_, '.*I Ii."."'. lill f,! 111::'...llll' 10 1:'.HMr.~ 01*11.:.111:~. to~iD1l1<mS 18.B
/
DPR-25 I~STRt1M...'l:"Nl'AT!CN TP.AT tNITL-~TES ROD BLOc~
Table 3.2.3 C.r>~=<-.bl~ *In::;t.*
cr.a:'l:v:~ls Per
~::in Sv::;tc~(l) Instr~c~n~t~~~~....;..~~~~-!--=--=T~r-i~~;-::Le=-=-~~-e~l~S~~~t~t~i~~~*a::;.__
l A??.!1 upscale (flow bi~s) (7) '°( **
- . o.5awn + 50 J LTPF TPr" (2)
AP~l -upsca!.~ (~e!'u<?l ~nd Startup/Hot ~ 12/125 full ~ca.le Stanoby r.:oo~)
2 A?f-l-1 do*wnscale ( 7) ~ 3/125 full scale 1
- Red bloci<:. moni~or up~cale (flow bias) (7l i~-
. 0.65 w0 + 42 ( 2) l 3
3 Rod block monitor IP~l IRM dcwnse&le (3) up~cale
- dO'A~scale (7) Z 5/125 full
.-> 5/125 scale full seal~
~108/125 full.seal~
3 Ir""~ det'?ctor not fully ins~rted
7.(S) SRM detector not in ctartup posi~ion (4)
.e
---_:.. 2(5)(61
r-*\
i .
TA3!.::: 3.2.3 (cont) DPR-25
~:otcs:
- 1. For the Star'ct;.p/~ot Standby a:ld Run positio:ls of the F.eactor ?-~'Jee Selector Switch,.
there* shaJ_l be two cpcrahic or trippzcl trip zys'.:cns f-::>r c~ch function, e;-:ccpt t~c S:i:..'~ rod blo6:s, IRM up5c~le, IR:*'l cio"m:.~cal.:? and !?..l*! <!t?t~ctor r.o~ ful!.y insert~d in l
t.!~ co;:e n~~o*.. no.:. b :? oper ...".ln po=a ..::ton an d *-\.
It
c..c-.*:r.scc:i l e, i\?.?.:*:
upscale (flow bias), RBM upscale, and RBM downscale need not be operable in the Startup/Hot St~r.db*,r :1:cc.i.c. If t11~ first col\:rr.;i c~:mot be ~~::.:.for o~:? of the t'.*~o tri? sys'tc~s, thi~ *c~~d{t.icn inciy c:;,:ist for t;.p t.o se*:cn :1.~y~ v:r.cvidcd tf..?:\: c1t:ring tf:(!t tir::c the operable system is functionally tcstcil im~cdi~tc~y an1 dnily thcrc~ftcr: if this co::ci t. ioa la st::: lons~r than zcvcn d':y:; the sys ten shall be tr ip?sd. If the first colu~n ca11not be m~t for b6th trip sy~tc~s, the systc~s shnll be tripped.
12- W~- nercent nf drive flo~ requ1red to produce a rated core flow of 98 Ml'bin/hr.:
- 3. IP. .M c:iownscule rn~.y be bypassed when it is on its lowest_ rc:nge~
- 4. Tnis function may be bypassed -when th~ count rate is ~100 cps.
- s. One of the fo*.ir S?..1*1 inputs n<J.y be byp~sse_d.
- 6. This SP. n f"..lnction rna~t be bypnssed in the* higher IRM ranges when the IR.1'1 U:;?scale red block .is opcr<ibl~. e
- 7. Not required while performing low power physics tests at atrnospn~ric pressure during or after refueli:-ig at power levels not to exc(?~d 5 r-:.w (t}.