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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q4981999-09-10010 September 1999 Proposed Tech Specs Clarifying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits & Adding Ref to Caldon TR for LEFM ML20211G3221999-08-26026 August 1999 Proposed Tech Specs 4.0.6 Re SG Surveillance Requirements ML20210R7091999-08-13013 August 1999 Revised Proposed Tech Specs for LAR 98-010,proposing Rev to TS Table 3.3.1-1, Rt Sys Instrumentation & TS Table B 3.3.1-1, Rt Sys Setpoints ML20209E1861999-07-0909 July 1999 Proposed Tech Specs,Adding Reactor Core Safety Limit Figures to Section 5.6.5 of Ts,Clarifying That Overpower N-16 Setpoint Remains in TS & Reflecting NRC Approval of TRs Used to Determine Core Operating Limits Presented in COLR ML20212J4251999-06-23023 June 1999 Proposed Tech Specs,Revising EDG Start Be Emergency Start Instead of Normal Start Following Loss of Offsite Power ML20195E5401999-06-0404 June 1999 Proposed Tech Specs Pages 3.2-6,3.4-24,3.4-25,3.7-23,3.7-30, 3.8-25,3.9-9,3.9-10 & 4.0-2,provided as Addl Aditorial Changes Supplementing LAR 99-001 ML20195B6461999-05-27027 May 1999 Marked-up TS Pages Re LAR 99-004,changing Plant Battery Surveillance ML20195B6771999-05-24024 May 1999 Proposed Tech Specs Relocating Parameter Limits Allows for Available Operating & Analytical Margins to Be Used in Most Efficient Manner ML20206G7111999-05-0404 May 1999 Proposed Tech Specs Revising Surveillances Associated with Plant Battery & EDGs & Miscellaneous Editorial Corrections ML20198J3171998-12-21021 December 1998 Proposed Tech Specs,Proposing Changes Administratively for Unit 1 & Increasing Licensed Power for Operation of Unit 2 to 3445 Mwt ML20198J2541998-12-18018 December 1998 Proposed Tech Specs Sections 1.0,3.1,3.3,3.4,3.6,3.7,3.9 & 5.0,converting to ITS ML20198J5211998-12-17017 December 1998 Corrected Tech Specs Pages for Section 3.8 to 971211 Submittal Re TS Conversion Application ML20197K0491998-12-11011 December 1998 Proposed Tech Specs Section 3.8, Electrical Power Systems, Converting to ITS ML20196C5361998-11-20020 November 1998 Proposed TS Converting to ITS Sections 4.0,3.4 & 3.6 ML20195F1751998-11-13013 November 1998 Proposed Tech Specs,Revising Administrative Controls Section to Include Configuration Risk Mgt Program Into CPSES TS ML20195F5291998-11-11011 November 1998 Proposed Tech Specs Revising Core Safety Limit Curves & Overtemperature N-16 Reactor Trip Setpoints for Unit 2 Cycle 5 ML20196B8811998-10-30030 October 1998 Proposed Tech Specs Section 3.3 Re Instrumentation ML20154R7861998-10-21021 October 1998 Proposed Tech Specs Section 3.7, Plant Systems ML20154S2901998-10-14014 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Control,Respectively ML20154C9101998-10-0202 October 1998 Proposed Tech Specs 4.0.6, SG SR, Adding Definitions Required for F* Alternate Plugging Criterion & Identifies Portion of Tube Subject to Criteria ML20153E2661998-09-24024 September 1998 Proposed Improved Tech Specs Sections 3.4, RCS & 5.0, Administrative Controls ML20237E8461998-08-28028 August 1998 Proposed Tech Specs Pages Re Sections 1.0,2.0 & 3.0 of Proposed TS Changes in 980707 & s,In Response to NRC RAI ML20236J3131998-07-0101 July 1998 Revised Proposed Tech Specs Pages Re Safety Injection Signal & Blackout Signal ML20249C6101998-06-22022 June 1998 Proposed Tech Specs Section 3.6 Re Conversion Application ML20216E6291998-04-0909 April 1998 Marked-up TS Pages,Reflecting Proposed Changes in Amends to Licenses NPF-87 & NPF-89 ML20216B1471998-04-0606 April 1998 Proposed Tech Specs,Allowing Plant to Continue to Operate W/O Having to Perform Portions of SRs ML20217A3901998-03-18018 March 1998 Proposed Tech Specs Surveillance Requirements 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a) at Power Re Enforcement Discretion ML20216H1361998-03-13013 March 1998 Proposed Tech Specs Re Electrical Systems Surveillance Requirements ML20248L3191998-03-12012 March 1998 Proposed Tech Specs TS 4.8.1.1.2f.4)b) & TS 4.8.1.1.2f.6)b) Re Request for Enforcement Discretion ML20216D6021998-03-0909 March 1998 Proposed Tech Specs Temporarily Removing Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of SRs 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a),for Unit 2 Only ML20203K8621998-02-27027 February 1998 Proposed Tech Specs,Increasing RWST low-low Level Setpoint ML20203J5211998-02-25025 February 1998 Proposed Tech Specs Page to Remove Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of Surveillance Requirements 4.8.1.1.2f.4(a) & 4.8.1.1.2f.7(a) Until Plant Startup Subsequent to Next Refueling Outage ML20202B1641998-02-0505 February 1998 Proposed Tech Specs Bases 3/4.7.1.5 Re Main Steam Line Isolation Valves ML20212C3881997-10-24024 October 1997 Proposed Tech Specs Re Revised Core Safety Limit Curves & Revised Overtemperature N-16 Reactor Trip Setpoints ML20141G1941997-05-16016 May 1997 Proposed Tech Specs,Consisting of Change Request 97-002 Re Rev to Unit 2 Rt Setpoint ML20134B9801996-09-19019 September 1996 Proposed Tech Specs Re Inverter/Battery Charger Mod ML20116F0471996-08-0202 August 1996 Proposed Tech Specs Re Increase in Allowed Outage Time for Charging Pump from 72 H to 7 Days ML20116E8651996-07-31031 July 1996 Proposed Tech Specs Modifying Inverter/Battery Chargers by Incorporating Listed Changes Into CPSES Units 1 & 2 TSs ML20116F3711996-07-31031 July 1996 Proposed Tech Specs 6.9.1.6b Including TR, SBLOCA Analysis Methodology, in List of NRC-approved Methodologies & Rev of Unit 1 Rx Trip Setpoints ML20115E8041996-07-10010 July 1996 Proposed TS 3/4.7.11,revising Lco,Actions & SRs to Take Credit for Addition of Train Oriented Fan Coil Units for Each UPS & Distribution Room ML20115C9461996-07-0909 July 1996 Proposed Tech Specs Re Steam Line pressure-low Allowable Value ML20113B5891996-06-21021 June 1996 Proposed Tech Specs,Removing Request to Relocate MSIV Full Closure Time Requirement to Program Administratively Controlled by TS & Revising Associated Bases to Include Info to Clarify Expanded Bases Specific to CPSES ML20106G8231996-03-13013 March 1996 Proposed Tech Specs,Supplementing LAR-95-007,revising TS LCO 3.9.4 to Allow Both Doors of Personnel Airlock to Remain Open as Long as One Pal Door Capable of Being Closed ML20101C5681996-03-12012 March 1996 Proposed Tech Specs 3/4.6.1 & 6.8.3g to Implement New Containment Leakage Rate Testing Program Required by 10CFR50 App J,Option B ML20100J0791996-02-22022 February 1996 Proposed Tech Specs 3/4.9.4,revising Units 1 & 2 TS Bases Allowing Both Doors of Pal to Remain Open as Long One Pal Door Is Capable of Closing ML20096B3281996-01-0505 January 1996 Proposed TS Re Wide Range RCS Temp.-Th Remote Shutdown Indication ML20095E8311995-12-15015 December 1995 Proposed TS Bases 2.2.1,deleting Unnecessary Details Re Time Delay Requirements for Undervoltage & Underfrequency RCP Trip Setpoints ML20094N6201995-11-21021 November 1995 Proposed Tech Specs,Allowing Containment Pal Doors to Remain Open During Movement of Irradiated Fuel & During Core Alterations for Plant ML20094N9011995-11-21021 November 1995 Proposed Tech Specs,Incorporating Revised Core Safety Limit Curves & Revised N-16 Overtemp Reactor Trip Setpoints, Resulting from Reload Analyses for CPSES Unit 2,Cycle 3 ML20087L4581995-08-15015 August 1995 Proposed Tech Specs Removing Several Cycle Specific Parameter Limits & Adding Limits to COLR 1999-09-10
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q4981999-09-10010 September 1999 Proposed Tech Specs Clarifying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits & Adding Ref to Caldon TR for LEFM ML20211G3221999-08-26026 August 1999 Proposed Tech Specs 4.0.6 Re SG Surveillance Requirements ML20212H0771999-08-20020 August 1999 Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820. Page 119 in Unit 1 ASME Section XI of Incoming Submittal Not Included ML20212G0821999-08-20020 August 1999 Rev 4 to Augmented Inservice Insp Plan for Cpses,Unit 1 ML20210R7091999-08-13013 August 1999 Revised Proposed Tech Specs for LAR 98-010,proposing Rev to TS Table 3.3.1-1, Rt Sys Instrumentation & TS Table B 3.3.1-1, Rt Sys Setpoints ML20211M0041999-08-0505 August 1999 Rev 31 to Technical Requirements Manual ML20211G7401999-07-27027 July 1999 Revs 29 & 30 to Technical Requirements Manual (TRM) for Cpses,Units 1 & 2 ML20209E1861999-07-0909 July 1999 Proposed Tech Specs,Adding Reactor Core Safety Limit Figures to Section 5.6.5 of Ts,Clarifying That Overpower N-16 Setpoint Remains in TS & Reflecting NRC Approval of TRs Used to Determine Core Operating Limits Presented in COLR ML20212J4251999-06-23023 June 1999 Proposed Tech Specs,Revising EDG Start Be Emergency Start Instead of Normal Start Following Loss of Offsite Power ML20195E5401999-06-0404 June 1999 Proposed Tech Specs Pages 3.2-6,3.4-24,3.4-25,3.7-23,3.7-30, 3.8-25,3.9-9,3.9-10 & 4.0-2,provided as Addl Aditorial Changes Supplementing LAR 99-001 ML20195B6461999-05-27027 May 1999 Marked-up TS Pages Re LAR 99-004,changing Plant Battery Surveillance ML20195B6771999-05-24024 May 1999 Proposed Tech Specs Relocating Parameter Limits Allows for Available Operating & Analytical Margins to Be Used in Most Efficient Manner ML20206G7111999-05-0404 May 1999 Proposed Tech Specs Revising Surveillances Associated with Plant Battery & EDGs & Miscellaneous Editorial Corrections ML20206Q0311999-04-16016 April 1999 Rev 28 to CPSES Technical Requirements Manual ML20205Q1681999-04-14014 April 1999 Rev 27 to CPSES Technical Requirements Manual ML20207F3511999-02-25025 February 1999 Fire Endurance Test to Qualify Protective Envelope for Class IE Electrical Circuits ML20203B0011999-01-25025 January 1999 Rev 10 to Security Training & Qualification Plan ML20211C1071999-01-15015 January 1999 Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval ML20198J3171998-12-21021 December 1998 Proposed Tech Specs,Proposing Changes Administratively for Unit 1 & Increasing Licensed Power for Operation of Unit 2 to 3445 Mwt ML20198J2541998-12-18018 December 1998 Proposed Tech Specs Sections 1.0,3.1,3.3,3.4,3.6,3.7,3.9 & 5.0,converting to ITS ML20198J5211998-12-17017 December 1998 Corrected Tech Specs Pages for Section 3.8 to 971211 Submittal Re TS Conversion Application ML20197K0491998-12-11011 December 1998 Proposed Tech Specs Section 3.8, Electrical Power Systems, Converting to ITS ML20196C5361998-11-20020 November 1998 Proposed TS Converting to ITS Sections 4.0,3.4 & 3.6 ML20195F1751998-11-13013 November 1998 Proposed Tech Specs,Revising Administrative Controls Section to Include Configuration Risk Mgt Program Into CPSES TS ML20195F5291998-11-11011 November 1998 Proposed Tech Specs Revising Core Safety Limit Curves & Overtemperature N-16 Reactor Trip Setpoints for Unit 2 Cycle 5 ML20196B8811998-10-30030 October 1998 Proposed Tech Specs Section 3.3 Re Instrumentation ML20154R7861998-10-21021 October 1998 Proposed Tech Specs Section 3.7, Plant Systems ML20154S2901998-10-14014 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Control,Respectively ML20154C9101998-10-0202 October 1998 Proposed Tech Specs 4.0.6, SG SR, Adding Definitions Required for F* Alternate Plugging Criterion & Identifies Portion of Tube Subject to Criteria ML20153E2661998-09-24024 September 1998 Proposed Improved Tech Specs Sections 3.4, RCS & 5.0, Administrative Controls ML20237E8461998-08-28028 August 1998 Proposed Tech Specs Pages Re Sections 1.0,2.0 & 3.0 of Proposed TS Changes in 980707 & s,In Response to NRC RAI ML20154C4511998-07-20020 July 1998 Interim Change Request ISI-1R5-01, Unit 1 ISI Plan,Rev 5 ML20236T9931998-07-20020 July 1998 1RF06 ISI Summary Rept First Interval,Third Period,First Outage for CPSES Unit 1, Commerical Operating Date 900830 ML20236J3131998-07-0101 July 1998 Revised Proposed Tech Specs Pages Re Safety Injection Signal & Blackout Signal ML20249C6101998-06-22022 June 1998 Proposed Tech Specs Section 3.6 Re Conversion Application ML20216B2811998-04-24024 April 1998 Rev 13 to Cpses,Units 1 & 2,IST Plan for Pumps & Valves First Interval ML20216E6291998-04-0909 April 1998 Marked-up TS Pages,Reflecting Proposed Changes in Amends to Licenses NPF-87 & NPF-89 ML20216B1471998-04-0606 April 1998 Proposed Tech Specs,Allowing Plant to Continue to Operate W/O Having to Perform Portions of SRs ML20217A3901998-03-18018 March 1998 Proposed Tech Specs Surveillance Requirements 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a) at Power Re Enforcement Discretion ML20216H1361998-03-13013 March 1998 Proposed Tech Specs Re Electrical Systems Surveillance Requirements ML20248L3191998-03-12012 March 1998 Proposed Tech Specs TS 4.8.1.1.2f.4)b) & TS 4.8.1.1.2f.6)b) Re Request for Enforcement Discretion ML20216D6021998-03-0909 March 1998 Proposed Tech Specs Temporarily Removing Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of SRs 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a),for Unit 2 Only ML20203K8621998-02-27027 February 1998 Proposed Tech Specs,Increasing RWST low-low Level Setpoint ML20203J5211998-02-25025 February 1998 Proposed Tech Specs Page to Remove Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of Surveillance Requirements 4.8.1.1.2f.4(a) & 4.8.1.1.2f.7(a) Until Plant Startup Subsequent to Next Refueling Outage ML20203J6151998-02-24024 February 1998 Rev 26 to Technical Requirements Manual ML20217P1531998-02-12012 February 1998 Rev 2 to ISI-2R2-01, Unit 2 ISI Plan ML20202B1641998-02-0505 February 1998 Proposed Tech Specs Bases 3/4.7.1.5 Re Main Steam Line Isolation Valves ML20217P2961998-01-30030 January 1998 Rev 5 to Unit 1 ISI Program Plan ML20202E5981997-11-25025 November 1997 Rev 12 to CPSES Units 1 & 2 IST Testing Plan for Pumps & Valves,First Interval ML20212C3881997-10-24024 October 1997 Proposed Tech Specs Re Revised Core Safety Limit Curves & Revised Overtemperature N-16 Reactor Trip Setpoints 1999-09-10
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Att'achment to TXX-92169
~Page 2 of-7 9
' BLE ?. 3-1 (Centi vec)
'ABLE NOTAT:245 a
Only if the reacter trio treaxers rapren to ce in the closec :osition saa tre Centrol Roc Orive System is capacle of roc .itnara-al.
Uselo. tne -E ('. ne eciate Range Neutrcn Flux :nterlock) Set:cint.
C Below tne P-10 (Lc Se:00 int P0'.er Range Neutron Olux Intertoc()'5et;;:-t d
Atove the-P-7 (At Oc er) Setccint
'ine applicable MODES and ACTION statements for these channels notec in Tacle 3.3-2 are more restrictive arc therefore, applicacle.
f A0cve the P-3 (3-leep flow permissive) Setpoint.
9Atove the P-7 anc telc- the 0-S 5et0ciats.
h The caren cilution flux coucling signals may te blocked curing reactc startut i Above tne D-9 (Reacter trip on Turtine trio Interlock) Setpoint, ACTION 5TATEMENTS ACTION 1 - Witn the nutter af ODERABLE channels are less inan the * " u-Cnanreis CPERABLE recuirement, restore ~'e inopera le cra" ei to 0:ERABLE status witnin AB hours er :- in HOT STAND 3Y .ita'n r tne nemt 6 nours.
ACT!:N 2 '.i tn t"e cutter of 0;ERABLE cnannels 0 - less tnan tr4 Tctal Numcer of Cnannels, STARTUP anc/or DOWER OPERATION maj :veceec prc.: cec tre follo ing concitions are satisfied;
- a. e inoceraole cnannel is placec in the tr i ccec conciti:n itnin 6 nours,
- c. The Minimem Cnannels OPERABLE recuirement is met; nc.e.er, tne inoptratie cnannel may ce byoassed for uo 10 A n0urs
'or surveillance testing of other enannels per 5:ecifica. ion A.3.1.1, and
- c. E4 tner, THERMAL 10WER is restricted to less than er e:aal to 75'. of RATED TnERMAL POWER and tne Power Range Neutron i:
rb* Trio set;oint is recutec to less tnan or ecual ::
'EEi of DATED inERMAL PCwER ithin A nours; Or, tre L
- c at; ANT 00wE; TILT RATIO is monitorec at least orce
- e"
'.2 s ues :er 5:ec fication A.2.A.2 m -
E U Y}' fY"fmp. , * , / y' p ,e f ,,
y m/y'_f~ff"\/',t . ~.
- Bcron inlution Flux Doubling requirements become effective for Unit I six months after criticality for Cycle 3 ana for Unit 2 six months after initial criticality. ,
s 4 m%%utCV lCVA%C-E SEl.4
., f;! ' . !2 3-5
+ - ~, _ , , , . . - , - -- - . - _ . - -
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Attaqhment to TXX-92169 Page 3 of 7 : ::s s': EuEs'5 :::~t %ec) 4 ACT:CN 3 ait' t~e nLT:er of cr3nnel s C DERAB LE o*e les s t'en t*.e Y -'*.-
Cnannels 0:ERABLE recuirement and itn the TwE: MAL ;CaER 1e.e'
- a. Sele. the ;-6-(Inter Eciate Range Neutr0n 81ui :-terio ()
Setooint, restere the inoceracle channel to CPERaBLE status Or1;r t: intress'ag THERMAL DO'nER accve t e ;-5 let;oint,
- t. A00ve the ?-6 (Inter?ef ate Range Neutron Clus ;*ter!O;* )
Set:01nt tot cele 10'. of RATED inERMAL POWER, restore t*e l inocerstle channel to OPERABLE status crior to increasirg ]
THERMAL PC=ER above 10% of RATED THERMAL POWER. '
1 C' CN 4 - with tne numrer O' 0?ERABLE :nannels one less tnan ne Mini *u m Channels OPERABLE recuirement, suspend all coerations '".ol<4ag
- Ositive reacti.ity cnanges.
[:,C':CN~~WMmn,-fr wverernm V"'mm Ej 'ith tne r ecer of CPE:AELE cnannels one less inan the v i ra a 5 Cnannels CPERAELE re:uirement, restore tne inoperacle :nanrel 5 6
to C;E;ABLE status itnin S nours ct .ithin t*e nest nea r c:en wA :ne reactor trip creatertf' suspene ali cherations in. chir; i
2:sitise reacti'.it. nanges.pna verifv eitner valve .M-5d 5 h
/. cr sabes 10 5-556 0, FCV-l'.1B , 1C5-543'9, IC 5-3441, an are cicsec an: securea in position, anc verifv in's oesiti:n at 1:5-5453 5 ioast - re rer 14 davs ttere3fterj W1* no cnanreis 0;E aE'.E
!)J
[
cottlete &t*e 30cse actions within 4 *ours.janc ver1+y tre .
J 1resitises -' te anece al tes at least -en ner la ca s taeeaa'tsr )
/p.( , ,
N N A ,. - s - W L - L.- % ~ '
..N n - altn the nutter of U-ts eL: channels o + less inan t~e :;3
/
%?ter f nannels, 37ARTUP an0/or PC'n'E; OPERAIICN ,aj Or::eeC
- r0sice
- tne f0llowing Conditions are 50*isfied:
- a. ne inoperaDie cnannel is place: 'r t re t r';0e0 ::"C' t : 0
.itnin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and Tne Minim e Cnannels ODERABLE recu!"eTe"t 's *et. ";*e e"-
tne incoeracle enannel may be cypassec fc u: : a ncurs f0r surveillance testing of other :nannels ;er Specification 4.3.1.1.
ACT:CN 7 - With less inan the Minimum Number of Channels CPERABLE. *'tr 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cetermine by 00$ervation of the associated erm is' e annunciator in:c (s) that tne interloc( is in its #ea 're: state f or the existing :lant concition. cr accly 50ec1'i:at' - : ..:
?
,"l'f ,y.- rYnV ,f y- 3/ V', f./ , /* /
, , ~~,- , ,
} \
- Boron Oilution Flux Doubling requirements become effective for Unit 1 six months (
after criticality for Cycle 3 and for Unit 2 six months after initial criticality. !
vv wwMx,wagfv%n As/M '% ~
. - . , . - , . - - - - - - - . . . . . . . . - - - . . - . . . . . - . - . . ~ . . .. - -.
]ttac,hment-to TXX-92169-lPage 4 of 7 1N_SLRT A ACTION 5.'2* - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or withh the next hour-verify either valve 105-8455 or valves ICS-8560, FCV-111B, 10S-8439, 1C5-8441, and 1C5-8453 are closed and secured in position, and verify this position at least once per 14 days thereafter. With no channels OPERABLE, complete the above actions within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and verify the positions of the above valves at least cace per 14 days thereaf ter, i
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Jttachment to TXX-92169 Page 6 of 7 I:.BLE 4. 3-1 ( Continueal TABLE NOTATIONS 3
Only i' ine reactor trio creakers 5accen to be in the closed cosition anc tre Controi : 0 Orive 5;, stem is capable of roc witncrawal.
~3elow- Di (:-ter ec'3ie Range Neutron Flux Interlock) Settoint.
'Selo== P-13 (Lc. 5et;oint Dower Range Neutr0n Flux Interlock) $etpoint.
Acove the P-7 ( At Po er) Set 00 int.
'Above the P 9 (Reacter trip on Turbine trip Interlock) Setpoint.
(1) If not per'ormed in previous 31 days.
(2) Com:arison of calorimetr,c to excore co er . and N-16 power indication atose 15% ;f RATED S EDMAL DOWER. Adjust excore channel and/or N-16 CNannel gains consistent with calorimetric co.er if absolute difference of the res ectise 4
channel is greater inan 2L The provisions of Specification 4.0.4 are not applicaDie for entry into MODE 1 or 2.
(3) Single coint cor arison of inc0re to encore AXIAL FLUX OIFFERENCE
.5', of RATED THERMAL DOWER. Recalibrate if ';he aDsolute 3 Cove difference is greater t~an or equal to 3L For the purpose of inese surveillance recuirements, "M" is defined as at least once cer 31 E~ 0.
Tne Orovisions :f 5pecification 4.0.4 are not ap; icable for entry i t:
MODE 1 or 2.
(4) Neutron and N-15 etectors may Oe excluded f rom 1-ANNEL CALIERAT!CN.
(5) Detector plateau curves small ce Octained and evaluatec. For the
- nter eciate ;arce Neutren Flux, Power Range Neutron Flux and N-15 ch3rrets a :rovisicrs ' 3:ecification 2.0.4 are not applicable for entr', ,nt:
CE 1 cc 2.
- ar te (5)- Inc:re Exc0-e Cali0rati:n. acove 75% of RATED TnERMAL POWER.
pur::se.cf t ese surveillance requirements "Q" is defined as at ! east once per 92 E:DC. Tne provisions of 5pecification 4.0.4 are not a;piic-able for entry into MODE 1 or 2.
(7) Eacn train shall be tested at least every 62 days on a STAGGERED TEST BASIS, (3) The MODES soeci"ed 'or these enannels in Table 4.3-2 are more restrictive anc t~erefore at:'icaele.
8 8 a (9) Quarterly surveillance in MODES 3 , 4 , and S shall also incluce verifica-tion tnat cermissises P-6 and P-10 are in tneir required state for exist-
. ing clant concitions by otservation of the permissive annunciator winco .
Ouarterly surveiliance snall include verification of tne 8cron Oilution Alarn Setcoint of ual to an increase cf twice the c:ent ithin a 10--tr :esstnanorp%
ute Oe"o4 mgw nyg,,y /vv,pc,p ,
e
/v
- Boron Dilution Flux Doubling requirements become ef fective for Unit 1 six monthsT after criticality for Cycle 3 and for Unit 2 six months after initial criticality.)
v Wm~xmmn~/
COMANCHE PEAK - UNIT 1 3/4 3-11
8ttachment to TXX-92169
'Page~7 of 7 . g,; ; 3.; : .. s
, 'AEl.E NO'A?IO N$ ( C:St'nue0)
( * :i ) 5etooint <erification 's not acclica0le.
(11) ?"e TRIP ACTUAIING CE < ' E COEU AI!CNAL IE 5I in3I' 'nceceacentl y ser'#j tae C ;E R t.B I L I! f of :ne edervoltage arc Snunt trio atta: rents of :ne -eact:-
trip Oreakers.
(12) At ' east crce er 13 T0rtas 1,riag saut00an. .eri'j t'at On 5 S i v'ite:
Soran Oil uti:n 01a4 C aci'.g test 59;nal tae rmal T4:$ c'5crarge salses cl:5 and tFe teatri'ugal caarging pu?:5 Sv tion valves from the Ra57 0:e (13) With the hign voltage setting ,>aried as rec:mmencea Oy the manufacturer, an initial ciscriminat:r Dias curse in3'l Oe ?easured for each detector.
Su05ecuent Oiscriminat:r Dias curves snail be Obtained, evaluated and
- .? pared to t*e initial curwes (lA) The TRIP ACTUATING CEVICE 00ERAI CNat TEST snali incepencently .eri', te OPERASILIIY cf t*e uncersoltage and 5^unt trio :ircuits for the Manual Reactor TriD Function. ?"e test 5*31' also verif., the OPERABIL Of e
Sy; ass Breaker trio fr: sit (51 (15) .::al manual snu nt t*i; : rice t: ;;! a c i:'; t r e a ke r i n service.
(16) Awt0matic undervoltage tm ;.
t i
)
l l
7ppfs.prf'fVVvm o. ,- ,yp. P/x,., %
c 1
- Boron Dilution Flux Doubling requirements become effective for Unit 1 six months
\ w after criticality n for Cycle p-~n-- 3 and for Unit 2 six months after initial - -y criticality CCMANCHE PEAK - UNII 1 3, a 3 - 12 1
l l.