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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
[Table view] |
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4 E
ATTACHMENT 2 PROPOSED STAT 10fl SERVICE WATER SYSTEM TECHNICAL SPECIFICATION P
PDR
Attachment 2 to TXX-92260
- PAge 1 of 6 PLANT SYSTEMS 3/4.7.4 STATION SERVICE WATER SYSTEM DRAFT LIMITING CONDITION FOR OPERATION t least two independent station service water loops per unit and he cross-c nect between the station service water systems of each unit s 11 be
, OPERABLE. In addition, the cross-connect valves XSW-0006, XSW-0007, SW-0008, I
! XSW-0028 an XSW-0029 shall be capable of being opened (from the m n control room) to pro e a flow path between the two units.
j APPLICABILITY: DES 1, 2, 3, and 4.
f ACTION:
Both Units in MODES 1, , 3 or 4.
- a. With only one s ation service water loo 'per unit OPERABLE, restore at least two loo per unit to OPERAB status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or for the unit with the noperable statio service water i.,op be in at least HOT STANDBY thin the next. hours and in COLD SHUT 00WN within the following 30 hou .
- b. With one or more of the rossfconnect valve (s) inoperable and not capsble of being opened r ffi the control room), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> re-store the valve (s) to OPE LE status or open the affected valve (s),
.and maintain the affecte v ve(s) open; otherwise be in at least HOT STANDBY within the next ho s and in COLD SHUTOOWN within the fol-I
/ lowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
One unit in Modes 1, 2, 3 or and one unit s Mode 5 or 6.
i a. . Verify that at 1 st one pump in the hutdown unit is OPERABLE and l, available to pr ide service water to e operating unit. If neither
! service water ump in the shutdown unit s OPERABLE, restore at least one pump to 0FERABLE status within 72 hou , or place the operating i' unit in at }4ast HOT STANDBY within the nex 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN w thin the following 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />s- .
- b. With on service water loop in the operating un1 inoperable, restore two lo s in the operating unit to OPERABLE statu within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or 3 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 /> d in COLD SHUT-1_ 00 with the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
\
\ c. W h one or more of the cross-connect valve (s) inoperabl and not
\ apable of being opened (from the control room), with 72 h rs restor the valve (s) to OPERABLE status or open the affected valve (s and
\'
maintain the affected valve (s) open; otherwise place the opera ng unit 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 COL SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Su h u.<t "A '
COMANCHE PEAK - UNITS 1 AND 2 3/4 7-14
Attachment to TXX-42260 n, - e DRAFT PLANT SYSTEMS cVRVEILLANCE REQUIREMENTS
/
ach station ser e water loop shall be demoastrats OPERABLE:
- a. At least once per days by . rifying t3a ch valve (manual,
/ power-operated, or a matic) ervicipq safety-related equipment that is not locked, se ed,orotp#wisesecuredinpositionisin its correct position; 7
- b. Atleastonceper92#aydy 4 11,.g cross-connect valves XSW-0006, j XSW-0007, XSW-000&dSW-0028, anNSW-0029 or verifying that the -
1 valves are loc,Ae6 open with power r ved; and
- c. At leas per 18 months during shutdo by verifying that each l sta eh service water pump starts automatica i on a Safety Injection
-- - J s_ t_e s COMANCHE PEAK - UNITS 1 AND 2 3/4 7-15
. _ _ _ _ - - _ _ _ _ _ - to TXX-92260 Page 3 of 6 _
INSERr" A
- 5 PLANT SYSTEMS 3/4.7.4 STATION SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two independent station service water loops per unit and the cross-connects between the station service water systems of each unit shall be OPERABLE.
APPLICABILITY: Units 1 and 2 in MODES 1, 2, 3 and 4 ACTION:
- a. With only one station service water loop in a unit OPERABLE, restore at least two loops per unit to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or for the unit (s) with the inoperable station service water loop, 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 SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,
- b. With one or more of the cross-connects inoperable, within 7 days restore the cross-connect (s) to OPERABLE status.
Otherwise, 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 SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE0VIREMEN_T_S _ _
4.7.4.1.1 Each station service water loop shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and
- b. At least once per 18 months, by verifying that each station service water pump starts automatically on a Safety injection test signal.
4.7.4.1.2 The cross-connects shall be demonstrated OPERABLE by cycling the cross-connect valves in the flow path or verifying that these valves are locked open at least once per 92 days.
COMANCHE PEAK - UNITS 1 AND 2 3/4 7-14 DRAFT
Attachment 2 to TXX-92260 Page 4 of 6 THSERT"h PLANT SYSTEMS LlHITING CONDITION FOR OPERATION 3.7.4.2 At least two independent station service water loops in the operating unit *, at least one station service water pump in the shutdown unit ** and the cross-connects from the OPERABLE station service water pump in the shutdown unit to the station service water loops of the operating unit shall be OPERABLE.
APPLICA31LITY: Unit 1 (Unit 2) in MODES 1, 2, 3 and 4 Unit 2 (Unit 1) in MODES 5, 6 and defueled -
ACTION:
- a. With one station service water loop in the operating unit inoperable, restore two loops in the operating unit 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 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 SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,
- b. With one or more of the cross-connects between the OPERABLE station service water pump in the shutdown unit and the station service water loops in the operating unit inoperable, within 7 days restore the inoperable valve (s) to OPERABLE status. Otherwise, place the operating unit 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 SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,
- c. If neither station service water pump in the shutdown unit is OPERABLE, restore at least one pump to OPERABLE status within 7 days or place the operating unit 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 SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEIL (ANCE REOUIREMENTS 4.7.4.2.1 Each station service water loop in the operating unit shall be demonstrated OPERABLE per the requirements of Specification 4.7.4.1.1.
4.7.4.2.2 The cross-connect (s) between the OPERABLE station service water pump in the shutdown unit and the station service water loops in the operating unit shall be demonstrated OPERABLE by cycling the cross-connect valves in the flow path or verifying that these valves are locked open at least once per 92 days.
- A Unit in MODE 1, 2, 3 or 4 is designated as the " operating unit".
- A unit in MODE 5, 6 or defueled is designated as the " shutdown unit".
COMANCHE PEAK - UNITS 1 AND 2 3/4 7-15 DRAFT
n tac a nt 2 ta Txx-N N N o. 3 ) nf 6 PLANT SYSTEMS BASES 3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the Component Cooling Water System ensures that suf-ficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses A Unit in Mo.bt.1,2,3 oY 4 Wil be.,
de si3114ted e oferaO4 God A Wt 3/4.7.4 STATION SERVICE WATER SYSTE;4 o McDE 9, C cn de wie wat be NNd'Decc i r" sNM 4 b,
The OPERABILITY of the Station Service Water System ensures that suffi- i cient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capa-city of this system, assuming a single failure, is consistent with the assump-tions used in the safety analyses. ~
s Hon In the event of a total loss of service water in one unit at Comanche Peak, q back@trt cooling capacity is ava lable via a cross-connect between the twogh units. The OPERABILITY of the unit cross-connect along with agservice water pump in the shutdown unit ensures the availability of sufficient redundant cooling capacity for the operating unit. The Limiting Condition of Operation
__ will ensure a significant risk reduction as indicated by the analyses of a loss
& M service water systemeccid:nt. The surveillance requirements ensure the
'. . short anct long-term OPERABILIT of th service water system and cross-connect between the two units Cven -
The d (<ess Camb u NS ^id ter system cross-connect between the two units consists of 60hh"N appropriate piping, valves ed N trr:ntatf0 5crest-cornect h$' he ischarge oT thejservice water pumps of the two units. 8, Operat h; the cross-connec , U@
thc r?p'y ddditional redundant cooling capac ty from one unit is availab e to the servi .
water system of the other unit.
3/4.7.5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either: (1) provide normal cooldown of the facility or (2) mitigate the effects of accident conditions within acceptable limits.
The limitations on minimum water level is based on providing a 30-day cooling water supply to safety-related equipment without exceeding its design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants," Rev. 2 (January 1976).
The limitation on maximum temperature is based on the maximum allowable compo-nent temperatures in the Service Water and Component Cooling Water Systems, and the requirements for cooldown. The limitation on average sediment depth is based on the possible excessive sediment buildup in the service water intake channel.
COMANCHE PEAK - UNIT 1 8 3/4 7-4
p.
AttechnentJ2 to TKX-92260-
- Pega 6,ot f
, PLANT SYSTEMS .
DRAFT BASES 1 INS E R T _ ' S ' _
~
A cross-connect valve is OPERABLE if it can be cycled or is locked- '
open;.however, r at least one cross-connect: valve between units is requir.eed to be maintained closed in accordance with GDC-5 unless due to total-loss of SSW pumps.for either unit. The OPERABLE pump.is manually essential heat loads,realigned and flow balanced to provide cooling to ,
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