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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems ML20095L0231995-12-22022 December 1995 Proposed Improved TS & Bases,Allowing Flexibility to Install Main Stack RMS (Mod 5386) W/O Need for Addl Licensing Actions & Addressing Annotations to Reflect pre- & post-mod Scenarios,Respectively ML20095J1321995-12-21021 December 1995 Proposed Tech Specs,Consisting of Change Request 95-08, Eliminating Outdated Matl from FOLs & Making FOL for Unit 2, Consistent W/Fol for Unit 3 ML20095J7011995-12-19019 December 1995 Proposed Tech Specs Re Administrative Change to Ventilation Filter Testing Program ML20095A1731995-11-30030 November 1995 Proposed Tech Specs,Changing Minimum Allowable Control Rod Scram Accumulator Pressure & Charging Water Header Pressure from Value of 955 Psig to Value of 940 Psig ML20094R2971995-11-22022 November 1995 Revised,Proposed TS Pages 147,157 & 158 Re Early Implementation of Improved TS Section 3.4.3 ML20094Q6801995-11-21021 November 1995 Proposed Tech Specs Re SR for High Pressure Test of HPCI & B 3.5-14 & B 3.5-28.Administrative Change Proposed to Eliminate Ref to Section Previously Eliminated ML20092A2141995-09-0101 September 1995 Proposed Tech Specs,Consisting of Change Request 95-07, Deleting License Condition 2.C ML20092A2841995-08-30030 August 1995 Proposed Tech Specs,Requesting Enforcement Discretion from Portion of FOL Condition 2.C ML20092B9871995-08-28028 August 1995 Proposed Improved Tech Specs ML20087E8881995-08-0404 August 1995 Proposed Tech Specs Re Implementation of New SR Associated W/Conversion to TS 1999-09-27
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20206C5821999-04-20020 April 1999 Rev 4 to RW-C-100, Solid Radwaste Sys Process Control Program (Pcp) ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20202E6251998-12-31031 December 1998 PBAPS Unit 2 Cycle 13 Startup Rept. with ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals ML20195J1541998-11-16016 November 1998 Rev D to PBAPS Emergency Preparedness NUMARC Eals ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20206C5711998-04-16016 April 1998 Rev 11 to ODCM for Pbaps,Units 1 & 2 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20202H4141998-01-31031 January 1998 Cycle 12 Startup Rept Unit 3 ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20141J0311997-05-0808 May 1997 Rev 7 to Pump & Valve IST Program Third Ten Yr Interval ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20217M8301997-01-30030 January 1997 Rev 10 to ODCM, for Peach Bottom Atomic Power Station Units 1 & 2 ML20134A6751997-01-24024 January 1997 Cycle 12 Startup Rept Unit 2 ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20138B0081996-09-27027 September 1996 Rev 3 to Solid Radwaste Sys Process Control Program (Pcp) ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems 1999-09-27
[Table view] |
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I ATTACHMENT 2 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 Docket Nos. 50-277 50-278 l
License Nos. DPR-44 DPR-56 TECHNICAL SPECIFICATIONS CHANGES Attached Pages Units 2 and 3 TS Page 3.7-4 TS Bases 3.7-7 TS Bases 3.7-13 l
l l
f P
]
p ESW System and Normal Heat Sink i
3.7.2
" SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in the pump bays of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the pump structure is a 98.5 ft Conowingo Datum (CD) and s 113 ft CD.
SR 3.7.2.2 Verifytheaveragewatertegeratureof 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l
normal heat sink is s 90*F SR 3.7.2.3
NOTE--------------------
Isolation of flow to individual components does not render ESW System inoperable.
Verify each ESW subsystem manual and power 31 days operated valve in the flow paths servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position, is in the correct position.
1 SR 3.7.2.4 Verify each ESW subsystem actuates on an 24 months actual or simulated initiation signal.
This note is voided af ter septenber 30, 1999. During the time period up to September 30, 1999, verify the average water temperature of the normal heat sink is 5 92*F.
PBAPS UNIT 2 3.7-4 Amendment No.
ESW System and Normal Heat Sink B 3.7.2
$ASES APPLICABLE The ability of the ESW System to provide adequate cooling to SAFETY ANALYSES the identified safety equipment is an implicit assumption (continued) for the safety analyses evaluated in Reference 1.
The ability to provide onsite emergency AC power is dependent on the ability of the ESW System to cool the DGs.
The long term cooling capability of the RHR and core spray pumps is also dependent on the cooling provided by the ESW System.
ESW provides cooling to the HPCI and RCIC room coolers; however, cooling function is not required to support HPCI or RCIC System operability.
The ESW System, together with the Normal Heat Sink, satisfy Criterion 3 of the NRC Policy Statement.
LC0 The ESW subsystems are independent to the degree that each ESW pump has separate controls, power supplies, and the operation of one does not depend on the other.
In the event of a DBA, one subsystem of ESW is required to provide the minimum heat removal capability assumed in the safety analysis for the system to which it supplies cooling water.
To ensure this requirement is met, two subsystems of ESW must be OPERABLE. At least one subsystem will operate, if the worst single active failure occurs coincident with the loss of offsite power.
A subsystem is considered OPERABLE when it has an OPERABLE normal heat sink, one OPERABLE pump, and an OPERABLE flow path capable of taking suction from the pump structure and transferring the water to the appropriate equipment.
The OPERABILITY of the normal heat sink is based on having a minimum and maximum water level in the pump bay of 98.5 ft ConowingoDatum(CD)and113ftCDgespectivelyanda j
maximum water temperature of 90'F The isolation of the ESW System to components or systems may render those components or systems inoperable, but does not affect the OPERABILITY of the ESW System.
APPLICABILITY In MODES 1, 2, and 3, the ESW System and normal heat sink are required to be OPERABLE to support OPERABILITY of the equipment serviced by the ESW System. Therefore, the ESW System and normal heat sink are required to be OPERABLE in these MODES.
(continued)
This note is voided after September 30, 1999. During the time period up to September 30, 1999, verify l
the average water temperature of the normal heat sink is 5 92*F.
PBAPS UNIT 2 B 3.7-7 Revision No.
l l
r 1
Emergency Heat Sink B 3.7.3 3ASES LCO -
Emergency heat sink water temperature is not addressed in (continued) this LCD since the maximum water temperature (90*F) has been demonstrated, based on historical data, to be bounded by the normal heat sink requirements (LC0 3.7.2, "
l Water (ESW) System and Normal Heat Sink").{,[mergency Service APPLICABILITY In MODES 1, 2, and 3, the emergency heat sink is required to be OPERABLE to provide a seismic Class I source of cooling water to the ESW and HPSW Systems when the normal heat sink is unavailable. Therefore, the emergency heat sink is required to be OPERABLE in these MODES.
In MODES 4 and 5, the OPERABILITY requirements of the emergency heat sink are determined by the systems it supports in the event the normal heat sink is unavailable.
ACTIONS M
With one required emergency cooling tower fan inoperable, action must be taken to restore the required emergency cooling tower fan to OPERABLE status within 14 days.
The 14 day Completion Time is based on the remaining heat removal capability, the low-probability of an event occurring requiring the inoperable emergency cooing tower fan to function, and the capability of the remaining emergency cooling tower fan.
M With the emergency heat sink inoperable for reasons other than Condition A, the emergency heat sink must be restored to OPERABLE status within 7 days. With the unit in this condition, the normal heat sink (Conowingo Pond) is adequate to perform the heat removal function; however, the overall reliability is reduced. The 7 day Completion Time is based on the remaining heat removal capability and the low probability of an event occurring requiring the emergency heat sink to be OPERABLE during this time period.
1 (continued)
]
This note is volded after September 30, 1999. During the time period up to September 30, 1999, verify the average water temperature of the normal heat sink is a 92*F.
PBAPS UNIT 2 B 3.7-13 Revision No.
1
I' l
ESW System and Normal Heat Sink 3.7.2 L
l'
- SURVEILLANCE REQUIREMENTS L
SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in the pump bays of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l
the pump structure is a 98.5 ft Conowingo Datum (CD) and s 113 ft CD.
SR 3.7.2.2 Verifytheaveragewatertegeratureof 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l
normal heat sink is s 90*F SR 3.7.2.3
NOTE--------------------
Isolation of flow to individual components does not render ESW System inoperable.
l Verify each ESW subsystem manual and power 31 days operated valve in the flow paths servicing safety related systems or components, that l
is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.7.2.4 Verify each ESW subsystem actuates on an 24 months actual or simulated initiation signal.
This note is voided af ter September 30, 1999. During the time period w to September 30, 1999, verify the average water temperature of the normat heat sink is 5 92*F.
1 l
l PBAPS UNIT 3 3.7-4 Amendment No.
ESW System and Normal Heat Sink B 3.7.2
- BASES APPLICABLE The ability of the ESW System to provide adequate cooling to SAFETY ANALYSES the identified safety equipment is an implicit assumption 1
(continued) for the safety analyses evaluated in Reference 1.
The j
ability to provide onsite emergency AC power is dependent on the ability of the ESW System to cool the DGs.
The long term cooling capability of the RHR and core spray pumps is also dependent on the cooling provided by the ESW System.
ESW provides cooling to the HPCI and RCIC room coolers; however, cooling function is not required to support HPCI or RCIC System operability.
The ESW System, together with the Normal Heat Sink, satisfy Criterion 3 of the NRC Policy Statement.
LC0 The ESW subsystems are independent to the degree that each ESW pump has separate controls, power supplies, and the operation of one does not depend on the other.
In the event of a DBA, one subsystem of ESW is required to provide the minimum heat removal capability assumed in the safety analysis for the system to which it supplies cooling water.
To ensure this requirement is met, two subsystems of ESW must be OPERABLE. At least one subsystem will operate, if the worst single active failure occurs coincident with the loss of offsite power.
A subsystem is considered OPERABLE when it has an OPERABLE normal heat sink, one OPERABLE pump, and an OPERABLE flow path capable of taking suction from the pump structure and transferring the water to the appropriate equipment.
The OPERABILITY of the normal heat sink is based on having a minimum and maximum water level in the pump bay of 98.5 ft ConowingoDatum(CD)and113ftCDgespectivelyanda l
maximum water temperature of 90 F The isolation of the ESW System to components or systems may render those components or systems inoperable, but does not affect the OPERABILITY of the ESW System.
APPLICABILITY In MODES 1, 2, and 3, the ESW System and normal heat sink are required to be OPERABLE to support OPERABILITY of the equipment serviced by the ESW System. Therefore, the ESW System and normal heat sink are required to be OPERABLE in these MODES.
(continued)
This note is voided after September 30, 1999. During the time period up to september 30, 1999, verify the everage water temperature of the normat heat sink is s 92'F.
PBAPS UNIT 3 B 3.7-7 Revision No.
I
y i
Emergency Heat Sink B 3.7.3 1 BASES LCO Emergency heat sink water temperature is not addressed in l
(continued) this LCO since the maximum water temperature (90*F) has been demonstrated, based on historical data, to be bounded by the l
normal heat sink requirements (LC0 3.7.2, l
Water (ESW) System and Normal Heat Sink").g",[mergency Servic APPLICABILITY In MODES 1, 2, and 3, the emergency heat sink is required to be 0?ERABLE to provide a seismic Class I source of cooling l-water to the ESW and HPSW Systems when the normal heat sink j
is unavailable. Therefore, the emergency heat sink is l
required to be OPERABLE in these MODES.
In MODES 4 and 5, the OPERABILITY requirements of the emergency heat sink are determined by the systems it supports in the event the normal heat sink is unavailable.
ACTIONS M
With one required emergency cooling tower fan inoperable, action must be taken to restore the required emergency cooling tower fan to OPERABLE status within 14 days. The 14 day Completion Time is based on the remaining heat removal capability, the low probability of an event occurring requiring the inoperable emergency cooing tower fan to I
function, and the capability of the remaining emergency l
cooling tower. fan.
l M
With the emergency heat sink inoperable for reasons other 1
than Condition A, the emergency heat sink must be. restored to OPERABLE status within 7 days. With the unit in this l
condition, the normal heat sink (Conowingo Pond) is adequate l
to perform the heat removal function; however, the overall reliability is reduced. The 7 day Completion Time is based on the remaining heat removal capability and the low probability of an event occurring requiring the emergency heat sink to be OPERABLE during this time period.
l (continued)
This note is voided efter September 30, 1999. During the time period ip to September 30, 1999, verify the average water temperature of the normat heat sink is 5 92*F.
PBAPS UNIT 3 B 3.7-13 Revision No.
f,.
.