|
---|
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
[Table view] |
Text
-__ _.
m i
i i
MARKED UP TECHt41 CAL $PECIFICATIONS-Enclosure 2 to 1XX-91299 !
Page 1 of 8 lr i
I 6
1
?
-i i
f I
'?
t I
.j
-l 1
I
.I t
I i
,i
-i f
A 9108190084 910809
. PDR ADOCK 05000445 P- PDR
.,- . .r,-r , -n, , , . , . . . . . _ , , , . . _ _ . _ , , _ - _ . , _ . , . . . _ _ _ . . . , , . . - . - . _ . - . _ . . _ . . . _ ...-,..-.......~.--/
Enclosure 2 to 1XX-91299 '
Page 2 of 8 REACT:vl+, C:9icCL 3,$tEus SHUTDOWN MARGIN T LESS TWAN OR EQUAL TO 200er LIMITING CONDITION FOR OPECATION 3.1.1.2 The 3rVTDC'aN MARGIN shall be greater than or ecual to iT';i, )
APPLICAB]LITY: MOCE 5. I
't_ v'5 _-
0, ACTICN:
1.31e With the SHUTDOWN MARGIN less tha f jdIa /k. immediately initiate anc continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7,000 ppm boron or equivalent until the required SHU100WN MARGIN is restored. i SURVEllLANCE REQUIREMENTS a .1. 4 The SHUTDOWN MARGIN shall be cetermined to be greater than er eac31 t o )X's 'k ;
/* a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> af ter detection of an inoperab'e control rod (l) and at least once per 12 nours thereafter while th- oc(s) is inoperacle .
If the inoperaDie control red is immovable untrippable, the SHUTDOWN MARGIN shall be verified acceptabi- .ith an increased allowance for the withorawn worth of the im eable or untrippable control rod (s); and
- c. At least once per 24 nours by consideration of the following factors:
- 1) Reactor Coolant System boron concentrat'en,
- 2) Control rod position,
- 3) Reactor Ccolant System average temperature,
- 4) Fuel burnup based on gross thermal energ/ generation, ;
- 5) xenon e acentration, and ,
- 6) Samarium concentration. I I
l l
t COMANCHE PEAK
L
- . . - = - w .- -r- r -
, , . .,.--,,w e- w - e---e v., wr.e-,-
l Q.g k w z ? *v TXX-91299 age 3 of B J!:.. Q .M :- S'5'(*5
- N f 5 OPERATING ti-1; 3G CONDITION FOR OPERATICN 3.1.2.2 At least t o of the fol'o.ing three t'oron injection flow paths shal' ce OPERABLE:
- a. The flow path from the boric scid storage tarls via either a boric acid transfer puftp Or a gravity feed connection and a charging pu p to the Reactor Coolant System (RCS), and
- b. Two flow paths from the refueling water storage tank via centrifugal charging pumps to the RC5 APPLICABILITC MODES 1, 2, 3, and 4.*
ACTION:
With only one of the above required boron injection flow paths to the RCS OPERABLE, restore at least too boron injectjomf4cy paths to the RC$ to OPERABLEstatuswithin72hoursorbein9t'lefstE STANDBY and borated to a SHUTDOWN MARGIN equivalent to at leQt A M,( 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least t o flow paths to OPE 'E status within thenext7daysorbeinCOLDSHUTDOWNwi\hin the next 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
( /.3 %
SURVEILLANCE REQUIREMENTS 4.1. 2. 2 At least t'.o of the aco.e required flow paths shall be demonstrated OPERABLE:
- a. At least once per 7 days by verifying that tt'e temperature o' the flow path from the boric acid storage tanks is greater than or eoual to 65 F when it is a required water source;
- b. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not lected, sealed, or otherwise secured in Dosition, is in its correct position; and
- c. At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2a, delivers at least 30 gpm to the RC5
- A maximum of two charging pumos shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 350'F except hen Specification 3.4.8.3 is not applicable. An inoperable pump may be energized for testing provided the discharge of the pump has been isolated from t'e RCS by a closed isolation valve (s) .ith power removed f rom the valve opera *.:<t i) or by a manual isolation sa'Se(s) secured in the closed position.
l COMANCHE PEA [ UNii 1 3.4 1-2
Enclosure 2 to TXX-91299 I
,P, age 4 of 8 i i
- EAC':.:' CN't. 5's'!v5 CHARGING PUMPS OPERATING LIMITING 00N0! TION FOR OPERATION I i
3.1.2.4 At least t o centrifugal enarging pumps shall be OPERABLE.
f Ao0LICABIL:Ti: MOCES 1, 2, 3*, and 4** *. v> j ACTICN: b With only one charging pump OPERABLE, r store at Igast two charging pumps to l OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or by laatleasp07STANDBYandboratedtoa ;
SHUT 00WN MARGIN equivalent to at led 54,M Jk/k at 200'F witnin the next ;
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />;restoreatleasttwoenargindpsmpsdeOPERABLEstatuswithinthenext 7 cays or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. ,
i SURVE!LLANCE REQUIREMENTS !
i 4.1.2.4.1 The required centrifugal charging pump (s) shtll be demonstrate
OPERABLE by testing pursuant to Specification 4.0.5. .
4.1.2.4.2 The required positive dis 013 cement charginc-pump shall be ;
demonstrated OPERABLE by testing pursuant to Specific . ion 4.1.2.2.c. '
4.1.2.4.3 Wheneser the temperature of one or more o+ *.re Reactor Coolant System (RCS) cold legs is less than or equal to 350** a maximum of two charging pumps shall be CPERABLE. except when Specif'.ition 3.4.8.3 is not !
applicaDie.
j When required, one charging pu.np shall be oemonstrated inoperable # at least f once per 31 cays by verifying that the motor circuit breakers are secureo in the open position, i
- The provisions of Specifications 3.0.4.Jnd 4.0.4 are not applicable for entry [
into MODES 3 anti 4 for the charging pumb declared inoperable pursuant to '
Specification 3.1.2.4 provided the charging pun.p is restored to OPERABLE [
5tatus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entering MODE 3 or prior to the temperature of l one or more of the RCS cold legs exceeding 375'F, .nichever comes first. .
- In MODE 4 the positive displacement pump may be used in lieu of one of the required centrifugal charging pumps.
t i An inoperable pump may be energized for testing provided the discharge of ,
the pump has been isolated from the RCS by a closed isolation valve (s) itn .
power removed from thi valve operator (s) or by a manual isolation val.e(s) :
secured in the closed position. '
i COMANCHE DEAK - UNIT 1 b 4 1- 10 j
Enclosure 2 to TXX 91299
. Page 5 of 8 REAC7!v C N* COL Sv57tus BORATED WATER SOURCES - OPERATING LIMITING CANOITION FOR OPERATION 3.1.2.6 As a minimum, the following borated water source (s) shall be CFERAELE as requireo by Soecification 3 L 2.2:
- a. A boric acid storage tant with:
- 1) A minimum indicated borated water level of 50%,
- 2) A minimum boron concentration of 7000 ppm, and
- 3) A minimum solution temperature of 65'F.
- b. The refueling water storage tank (RWST) with:
- 1) A minimum indicated borated water level of 95%,
- 2) A boron concentration between 2000 ppm and 2200 ppm,
- 3) A minimum solution temperature of 40'F, and
- 4) A maximum solution temperature of 120*C APPLICABILI?Y: MODES 1, 2, 3, and 4 ACTICN:
- a. With the Doric acid storage tank inoperable and being used as one h above required borated water sources, restort ,he tant to
[j CPEnABL T us witnin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within A t_. Dent 6 h rs and borated to a SHVIDOWN MARGIN equivalent to
/.3 N at least M /k'at 200'F; restore the boric acid storage tank to us thin the next 7 days or be in COLD SHUTDOWN within
- b. With the RWST inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
4 3/4 1-12 COMANCHE FEAK - UNIT.1
Enclosure 2 to TXX-91299
.(age 6of8 3,t 1 :t:: :.: ::st:et systrus EASES 3/4 1.1 !: RAT::N : N'RCL 3/A.1.1.1 nac 3 J.;.1.2 5HUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that: (1) the reactor can ce tace subtritical from all operating conoitions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptable 3 limits, and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
$HUTDOWN MARGIN reovirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,yg. The most restrictive condition occurs at EOL, with 7,,9 at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncon-trolled RCS cooldown. In the analysis of this accident, a mir' mum SHUT 00hN ,
MARGIN of 1,6* l,,dk is required to control the reactivity transient. i Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is e nsistent with FSAR safety a3aly11s_A n urotions. With ' '
less than 20f f the-teett+r44-y-4+an& dent &--rnutth 9 froma-pestehtt<htte (ILse-tesak 4c440*a-eeWm:I e iu a 1*c-::ttt-$Ht1TOOWtiAR0iff prev 4es
\doeevett-pMtec t4on. -
IN fitt A _
Since the actual overall core re' activity balance :omparison required by 4.1.1.1.0 cannot be performed until af ter criticalit:. s attained, this comoarison is not required (and the provisions of Spec fication 4.0.4 are not applicaole) for entry into any Operational Mode within the first 31 EFFC follo.ing N tial fuel load or refueling, 314.1.1.3 MODERATOR TEMPERATURE COErFICIENT The limitatiens on moderator temperature coefficient (MTC) are provideo to ensure that the value of this coefficient remains within tne limiting condition assum
The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conaitions in order to permit-an a: curate comparison.
The most negative MTC value equivalent to the most positive moderator density coefficient (MDC) was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions. These corrections COMANCHE PEAK
Enclosure 2 to TXX-91299 Page 7 of 8 INSERT A a SHU100WN MARGIN of 1.3X a k/k provides adequate protection and is based on the results of the boron dilution accident analysis.
Enclosure 2 to 1XX-91299 l Page 8 of 8 REaCTIV! :N :L 5'5'EuS.
BASES BCRATICN 5< STEMS (Continued) witn tne RCS tetoerature belew 200*F, one Boron Injection System is acceptable .itnout single failure consideration on the basis of the stable reactivit/ co cition of the reactor and the additienal restrictions orenicitug CORE ALTERATICN5 and positive reactivity char.ges in the event the single Boron Injection System becomes inoperable.
The limitation for a maximum of two charging Pumps to te OPERABLE and the requirement to verify one charging pump to be inoperable below 350'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.
The limitation for minimum solution temperature of the borated water sources are sufficient to pre boron concentratio / gent'9JFTC) acid crystallization with the highest allo aDie jg, The boron ca sa ility reyfired below 200'F is suf ficient to provide a SHUTOOWN MARGIN of 7.' Sk/Jrif ter menon decay and cooldown f rom 200'F to 140 F.
This condition reh W ei either 1.100 gallons of 7000 ppm borated water + rom the boric acid storage tanks or 7,113 gallons of 2000 ppm borated water from the RWST.
As listed below, the required indicated levels f: the boric acid storage tanks and the RWST include allowances for recuired/an! ~j tical volume, unusaole volume, measurement uncertainties (which include inst- cent error and tank tolerances, as applicable), system configuration requ 'ements, and other required volume.
Tank MODE 5 Ind. Unusable Required Measurement System Other sevel volume Volume Uncertainty Config. (gal)
(gal) (gal) (gal)
RWST 5,6 2 4'. 45,494 7,113 4% of span 57.957 N<A 1,2,3,4 95% 45,494 70.702 4% of span N/A 357,535' Boric 5,6 10% 3,221 1,100 6% of span N/A N/A Acid 5,6 20% 3,221 1,100 6% of span 3.679 N/A Storage (gravity feed) 1,2,3,4 Tank 50% 3,221 15,700 6% of span N/A N/A The OPERABILITY of one Boron Injection System during REFUELING ensures that this system is available for reactivity control while in MODE 6.
- Additional volume required to meet Specification 3.5.4.
COMANCHE FEAK - UNIT 1 B 3/4 1-3
- _