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| {{#Wiki_filter:}} | | {{#Wiki_filter:_ _ _ _ |
| | ENCLOSURE 3 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS INOPERABLE MAIN STEAM SAFETY VALVES , |
| | 1 JNTi.TRUCTIONS FOR INCORPORATION AND PROPOSED CHANGES TO THE l TECHNICAL SPECIFICATIONS ! |
| | The proposed change to the Vogtle Electric Generating Plant Technical Specification would be incorporated as follows: |
| | Removed Page Insert Page 3/4 7-l* and 3/4 7-2 3/4 7-l* and 3/4 7-2 B 3/4 7-1 and B 3/4 7-2* B 3/4 7-1 and B 3/4 7-2* |
| | * Overleaf page containing no change E3-1 9404120063 940331 PDR ADOCK 05000424 ' |
| | P PDR . |
| | |
| | TABLE 3.7-1 ! |
| | MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH j INOPERABLE STEAM LINE SAFETY VALVE 5 MAXIMUM NUMBER OF INOPERABLE MAXIMUM ALLOWABLE POWER RANGE SAFETY VALVES ON ANY NEUTRON FLUX HIGH SETPOINT OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER) 1 |
| | * 71 2 . |
| | * 51 3 |
| | * 31 I |
| | i l |
| | 1 l |
| | V0GTLE UNITS - 1 & 2 3/4 7-2 I _ _ _ . . _ _____ - _ _ _ - , _ .- ._____ |
| | |
| | 1 |
| | . [ 3/4.7 PLANT SYSTEMS |
| | ~ |
| | BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line Code safety valves ensures ths.t |
| | : the Secondary System pressure will be limited to within 110% (1304 psig) of j its der.ign pressure of 1185 psig during the most severe anticipated system operational transient. The maximum relieving capacity is associated with a Turbine trip from 100% RATED THERMAL POWER coincident with an nssumed loss of condenser heat sink (i.e., no steam bypass to the condenser). |
| | J The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1974 Edition. The total relieving capacity for all valves on all of the ! |
| | steam lines,is 18,607,220 lbs/h which is 117% of the total secondary steam flow l l |
| | of 15.92x10 lbs/h at 100% RATED THERMAL POWER. A minimum of two OPERABLE 4 |
| | safety valves per steam generator ensures that sufficient relieving capacity is , |
| | j available for the allowable THERMAL POWER restriction in Table 3.7-1. l I |
| | STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in Secondary Coolant System steam flow and THERMAL POWER required by the l reduced Reactor trip settings of the Power Range Neutron Flux channels. The Reactor Trip Setpoint reductions are derived on the following basis: |
| | J For four loop operation i SP - (X) - (Y)(V) x 09) x REPLACE NNITH INSENT I |
| | Where: |
| | SP - Redu Reactor Trip Setpoint in ercent of RATED THERMAL P0 R, V - Maximum number of inoper e safety valves per steam ne, 109 Power Range Neutron ux-Hig' ,ip Setpoint for our loop 4 |
| | operation, |
| | 'X - Total reliev g capacity of all safety ves per steam line in 1 / hour, and Y - Maxi m relieving capacity of an one safety valve in 1 hour. |
| | 4 V0GTLE UNITS - 1 & 2 B 3/4 7-1 Amendment No.O (Unit 1) |
| | Amendment No.39(Unit 2) |
| | |
| | ! l |
| | : 1. < |
| | i .i |
| | - j INSERT FOR BASES 3/4.7.1.1 Hi $ = (100/Q)(Wg htgN) |
| | K where: |
| | Hi $ = Safety Analysis power range high neutron flux setpoint, percent |
| | .Q = Nominal NSSS power rating of the plant (including reactor coolant pump. |
| | heat), MWt K = Conversion factor,947.82 (Btu /s) |
| | MWt ws = Minimum total steam flow rate capability of the operable MSSVs on any l one steam generator at the highest MSSV opening pressure including . |
| | tolerance and accumulation, as appropriate, in Ib/s. For example, if the maximum number ofinoperable MSSVs on any one steam generator is one, then washould be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating pressure, excluding the highest capacity MSSV. If the maximum number ofinoperable MSSVs |
| | - per steam generator is three then wg should be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating l pressure, excluding the three highest capacity MSSVs. |
| | = |
| | hrg Heat of vaporization for steam at the highest MSSV opening pressure l including tolerance and accumulation, as appropriate, Btu /lbm. |
| | l N = Number ofloops in the plant. |
| | l The values calculated must be reduced to acmunt for instrument and channel uncertainties (typically 9 percent power). Therefore, the maximum plam operating power level would then be lower than the reactor protection system setpoint by an appropriate operating margin. |
| | l l |
| | . -. . .,}} |
|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled ML20098A4861995-09-22022 September 1995 Proposed Tech Specs,Converting Existing VEGP TS Requirements to Format & Content of NUREG-1431 ML20086G5691995-07-0606 July 1995 Proposed Tech Specs Section 3.8.3.1,Page 3/4 8-15 Re Footnote & Bases & Expansion ML20085G7171995-06-14014 June 1995 Proposed Tech Specs,Clarifying in Revised Bases of 3/4 Chapter 8,that Alignment of Standby Auxiliary Transformer Intended to Be Temporary Alignment & Will Be Utilized When Normal Preferred Offsite Power Source,Rat Unavailable ML20083M0731995-05-12012 May 1995 Proposed Tech Specs Revising SR 4.1.6.2 to Support Exemption from 10CFR50,App J Type a Test Schedule ML20083A1391995-05-0202 May 1995 Proposed Tech Specs,Adding Automatic Load Sequencer to Plant TS ML20082D9881995-04-0404 April 1995 Proposed Tech Spec Page 6-7 Reflecting Corrected Terminology Re Composition of Plant Review Board ML20081J5031995-03-17017 March 1995 Proposed TS 3.9.4 Re Containment Airlock Doors to Be Open During Fuel Movement ML20081D1591995-03-17017 March 1995 Proposed TS Table 3.3-8, Accident Monitoring Instrumentation, Deleting Loop Numbers 551,552,553 & 554 ML20082E7731995-03-0404 March 1995 Proposed Tech Specs Re Plant Review Board Composition ML20080N2451995-02-28028 February 1995 Proposed Tech Specs Pages Re Accident Montoring Instrumentation 1999-09-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled 1999-09-22
[Table view] |
Text
_ _ _ _
ENCLOSURE 3 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS INOPERABLE MAIN STEAM SAFETY VALVES ,
1 JNTi.TRUCTIONS FOR INCORPORATION AND PROPOSED CHANGES TO THE l TECHNICAL SPECIFICATIONS !
The proposed change to the Vogtle Electric Generating Plant Technical Specification would be incorporated as follows:
Removed Page Insert Page 3/4 7-l* and 3/4 7-2 3/4 7-l* and 3/4 7-2 B 3/4 7-1 and B 3/4 7-2* B 3/4 7-1 and B 3/4 7-2*
- Overleaf page containing no change E3-1 9404120063 940331 PDR ADOCK 05000424 '
P PDR .
TABLE 3.7-1 !
MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH j INOPERABLE STEAM LINE SAFETY VALVE 5 MAXIMUM NUMBER OF INOPERABLE MAXIMUM ALLOWABLE POWER RANGE SAFETY VALVES ON ANY NEUTRON FLUX HIGH SETPOINT OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER) 1
i l
1 l
V0GTLE UNITS - 1 & 2 3/4 7-2 I _ _ _ . . _ _____ - _ _ _ - , _ .- ._____
1
. [ 3/4.7 PLANT SYSTEMS
~
BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line Code safety valves ensures ths.t
- the Secondary System pressure will be limited to within 110% (1304 psig) of j its der.ign pressure of 1185 psig during the most severe anticipated system operational transient. The maximum relieving capacity is associated with a Turbine trip from 100% RATED THERMAL POWER coincident with an nssumed loss of condenser heat sink (i.e., no steam bypass to the condenser).
J The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1974 Edition. The total relieving capacity for all valves on all of the !
steam lines,is 18,607,220 lbs/h which is 117% of the total secondary steam flow l l
of 15.92x10 lbs/h at 100% RATED THERMAL POWER. A minimum of two OPERABLE 4
safety valves per steam generator ensures that sufficient relieving capacity is ,
j available for the allowable THERMAL POWER restriction in Table 3.7-1. l I
STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in Secondary Coolant System steam flow and THERMAL POWER required by the l reduced Reactor trip settings of the Power Range Neutron Flux channels. The Reactor Trip Setpoint reductions are derived on the following basis:
J For four loop operation i SP - (X) - (Y)(V) x 09) x REPLACE NNITH INSENT I
Where:
SP - Redu Reactor Trip Setpoint in ercent of RATED THERMAL P0 R, V - Maximum number of inoper e safety valves per steam ne, 109 Power Range Neutron ux-Hig' ,ip Setpoint for our loop 4
operation,
'X - Total reliev g capacity of all safety ves per steam line in 1 / hour, and Y - Maxi m relieving capacity of an one safety valve in 1 hour.
4 V0GTLE UNITS - 1 & 2 B 3/4 7-1 Amendment No.O (Unit 1)
Amendment No.39(Unit 2)
! l
- 1. <
i .i
- j INSERT FOR BASES 3/4.7.1.1 Hi $ = (100/Q)(Wg htgN)
K where:
Hi $ = Safety Analysis power range high neutron flux setpoint, percent
.Q = Nominal NSSS power rating of the plant (including reactor coolant pump.
heat), MWt K = Conversion factor,947.82 (Btu /s)
MWt ws = Minimum total steam flow rate capability of the operable MSSVs on any l one steam generator at the highest MSSV opening pressure including .
tolerance and accumulation, as appropriate, in Ib/s. For example, if the maximum number ofinoperable MSSVs on any one steam generator is one, then washould be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating pressure, excluding the highest capacity MSSV. If the maximum number ofinoperable MSSVs
- per steam generator is three then wg should be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating l pressure, excluding the three highest capacity MSSVs.
=
hrg Heat of vaporization for steam at the highest MSSV opening pressure l including tolerance and accumulation, as appropriate, Btu /lbm.
l N = Number ofloops in the plant.
l The values calculated must be reduced to acmunt for instrument and channel uncertainties (typically 9 percent power). Therefore, the maximum plam operating power level would then be lower than the reactor protection system setpoint by an appropriate operating margin.
l l
. -. . .,