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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217D6351999-10-0808 October 1999 Proposed Tech Specs Sections 3/4.4.9 & B 3/4.4.9,revising Heatup & Cooldown Curves ML20211C2141999-08-19019 August 1999 Proposed Tech Specs,Revising Heatup & Cooldown Curves in TS 3/4.4.9, RCS P/T Limits ML20206T2141999-05-17017 May 1999 Proposed Tech Specs Section 3.7.1.3, CST - LCO, Revising Required Min Contained Volume of CST from 172,000 Gallons of Water to 179,850 Gallons of Water ML20197H5521998-12-0404 December 1998 Proposed Tech Specs Revising Testing Methodology Used by Vcns to Determine Operability of Charcoal Adsorber in ESF Air Handling Units ML20153C4001998-09-18018 September 1998 Proposed Tech Specs Incorporating W Beacon TR WCAP-12472-P-A to Augment Functionality of Flux Mapping Sys When Thermal Power Is Greater than 25% RTP ML20236G7581998-07-0101 July 1998 Proposed Tech Specs 4.7.7.e,removing Situational Surveillance Requirement of During Shutdown Following Specified Surveillance Interval of at Least Once Per Eighteen Months ML20202G6891998-02-0909 February 1998 Proposed Tech Specs Requesting Removal of Table 4.8-1, Diesel Generator Test Schedule & SR 4.8.1.1.3,Repts ML20141K2481997-05-21021 May 1997 Proposed Tech Specs Revising Testing Methodology Utilized by VCSNS to Determine Operability of Charcoal Adsorbers in Emergency Safeguards Features Air Handling Units ML20140C0641997-03-26026 March 1997 Proposed Tech Specs 3.8.1.1 Re AC Sources - Operating ML20140C1401997-03-26026 March 1997 Proposed Tech Specs Re Change to Core Alteration Definition ML20140C1071997-03-26026 March 1997 Proposed Tech Specs Re ECCS Charging/Hhsi Pump Cross Connect & mini-flow Header Isolation Motor Operated Valves ML20107G3511996-04-16016 April 1996 Proposed Tech Specs 3/4.6 Re Containment Sys,Per App J, Option B ML20101E6461996-03-19019 March 1996 Proposed Tech Specs,Consisting of Change Request 95-03, Enhancing LCO & SRs & Revises Bases for QPTR ML20097F4721996-02-10010 February 1996 Proposed Tech Specs,Revising Testing Methodology Utilized to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20096F0211996-01-18018 January 1996 Proposed Tech Specs,Lowering RWCU Isolation Setpoint from Reactor Low Level to Reactor low-low Level ML20095E6541995-12-0808 December 1995 Proposed Tech Specs,Consisting of Change Request 95-07 Re ECCS Pump Testing ML20095A8061995-12-0404 December 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 Correction of Bases 3/4 11-1 ML20094N8881995-11-21021 November 1995 Proposed Tech Specs,Allowing One Time Extension of AOT Specified in TS 3/4.5.2 for Each RHR Train from 72 H to 7 Days ML20094L3531995-11-14014 November 1995 Proposed TS 3/4.8.4.2,removing MOVs Thermal Overload Protection & Bypass Devices ML20094E4111995-11-0101 November 1995 Proposed Tech Specs,Consisting of Change Request 95-01, Permitting VCSNS to Operate at Uprate Power Level of 2900 Mwt Core Power When Unit Restarted After Ninth Refueling Outage ML20092A2371995-08-31031 August 1995 Proposed Tech Specs,Consisting of Change Request TSP 940002, Incorporating Revs to 10CFR20 ML20091L4541995-08-18018 August 1995 Proposed Tech Specs for Uprate Power Operation ML20087F8551995-08-11011 August 1995 Proposed Tech Specs Re Rev to TS Change 95-02 Concerning PORVs & Block Valves ML20087A2601995-07-28028 July 1995 Proposed Tech Specs Re TS 3/4.3.2,ESFAS Instrumentation,Sr 4.3.2.1 Being Revised to Exclude Requirement to Perform Slave Relay Test of 36 Containment Purge Supply & Exhaust Valves on Quarterly Basis While Plant in Modes 1,2,3 or 4 ML20086C0311995-06-30030 June 1995 Proposed Tech Specs Re PORVs & Block Valves ML20085K4591995-06-19019 June 1995 Proposed TS 3/4.6.2, Depressurization & Cooling Sys, Changing Required Test Frequency for Reactor Bldg Spray Nozzle Flow Test from Once Per Five Yrs to Once Per Ten Yrs ML20085L0411995-06-19019 June 1995 Proposed Tech Specs Re Deletion of Schedular Requirements for Type a Testing ML20080K1981995-02-21021 February 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 ML20078G9231995-01-30030 January 1995 Proposed Tech Specs Re Relocation of Seismic Monitoring Instrumentation ML20078B6121994-10-20020 October 1994 Proposed TS Page,Incorporating Approved Amend 116 & Requested SR Replacement TS Change ML20076J6691994-10-17017 October 1994 Proposed Tech Specs,Reflecting Relocation of Seismic Monitoring Instrumentation Lco,Srs & Associated Tables & Bases in TS Section 3/4.3.3.3 to FSAR or Equivalent Controlled Document ML20073D4111994-09-20020 September 1994 Proposed TS Pages,Including Page 6-16a,revising Rev Level & Date of WCAP-10216-P-A to Reflect Updated Methodology Used in Determining Plant Core Operating Limits ML20149G1301994-09-20020 September 1994 Proposed TS 3/4 5-6 Re Charging Pump Runout Flow Limit ML20071K3761994-07-22022 July 1994 Proposed TS Page 3/4 3-56,reflecting Required Action to Restore One Inoperable Hydrogen Monitor Channel to Operable Status,W/Less than Min Number of Channels Operable ML20070J7561994-07-20020 July 1994 Proposed Tech Specs,Permitting Alternative Equivalent Testing Methods to Be Performed on Diesel Fuel Purchased for EDGs & Changing Rev Level of WCAP-10216-P-A,that Will Be Used to Determine Core Operating Limits for Future Cycles ML20070J7881994-07-20020 July 1994 Proposed TS Pages for TS Tables 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints & 3.3-4, ESFAS Instrumentation Trip Setpoints ML20065B8361994-03-25025 March 1994 Proposed Tech Specs Pages for Missing Page Numbers of TS Pages Submitted in ML20064H9591994-03-11011 March 1994 Proposed TS 4.8.4.1.a.3,deleting Fuses Used as Penetration Overcurrent Protection Devices from SRs & from Bases B 3/4.8.4 ML20064H9251994-03-11011 March 1994 Proposed Tech Specs 3/4.4.9.3,changing AOT for RHR Suction Relief Valves from 7 Days to 72 H ML20064H4501994-03-11011 March 1994 Proposed Tech Specs Re Steam Generator Replacement ML20064G5541994-03-11011 March 1994 Proposed Tech Specs Re Limiting Safety Sys Settings for Reactor Trip Sys Instrumentation Trip Setpoints ESF Actuation Sys Instrumentation Setpoint ML20064C6421994-02-25025 February 1994 Proposed Tech Specs,Incorporating Current Provisions of 10CFR50.36(a)2 Re Semiannual Radioactive Effluent Release Rept to Be Submitted Annually Rather That Semiannually ML20062K6321993-12-13013 December 1993 Proposed Tech Spec Figures 3.9-1 & 3.9-2,permitting Storage of Fuel Assemblies in Regions 2 & 3 of Spent Fuel Storage Racks,Respectively ML20059G2901993-10-29029 October 1993 Proposed Tech Specs Supporting SG Replacement ML20056F7951993-08-24024 August 1993 Proposed Revised TS Re Emergency Feedwater Per 10CFR50.59 ML20045F7771993-06-30030 June 1993 Proposed Tech Specs SR 4.7.1.2 for Performance of Turbine Driven EFW Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psig ML20045C3441993-06-16016 June 1993 Proposed Tech Spec 4.7.1.2.a.2 Supporting Request to Perform Turbine Driven Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psig ML20044G7551993-05-25025 May 1993 Proposed Tech Specs Revising Page 3/4 7-4,re Changing TS 4.7.1.2.a.2,to Perform Turbine Driven Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psi ML20128H9781993-02-12012 February 1993 Proposed TS Modifying Insp Requirements of TS 3/4.4.5 Re SGs & LCO for 3/4.4.6.2 Re Operational Leakage to Establish Interim Plugging Criteria ML20128K1821993-02-10010 February 1993 Proposed Tech Specs Re Main Steam Safety Valves 1999-08-19
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D6351999-10-0808 October 1999 Proposed Tech Specs Sections 3/4.4.9 & B 3/4.4.9,revising Heatup & Cooldown Curves ML20211C2141999-08-19019 August 1999 Proposed Tech Specs,Revising Heatup & Cooldown Curves in TS 3/4.4.9, RCS P/T Limits ML20206T2141999-05-17017 May 1999 Proposed Tech Specs Section 3.7.1.3, CST - LCO, Revising Required Min Contained Volume of CST from 172,000 Gallons of Water to 179,850 Gallons of Water ML20212H4651999-05-0404 May 1999 Amend 17 to Training & Qualification Plan ML20197H5521998-12-0404 December 1998 Proposed Tech Specs Revising Testing Methodology Used by Vcns to Determine Operability of Charcoal Adsorber in ESF Air Handling Units ML20153C4001998-09-18018 September 1998 Proposed Tech Specs Incorporating W Beacon TR WCAP-12472-P-A to Augment Functionality of Flux Mapping Sys When Thermal Power Is Greater than 25% RTP ML20202C3271998-08-31031 August 1998 Amend 16 to Training & Qualification Plan ML20236G7581998-07-0101 July 1998 Proposed Tech Specs 4.7.7.e,removing Situational Surveillance Requirement of During Shutdown Following Specified Surveillance Interval of at Least Once Per Eighteen Months ML20153F9241998-04-23023 April 1998 Change A,Rev 10 to FEP-1.0, Fire Emergency Procedure Selection ML20153G7081998-03-30030 March 1998 Rev 2 to FEP-4.1, Plant Shutdown from Hot Standby to Cold Shutdown Due to Fire in Control Building ML20153F9691998-03-25025 March 1998 Rev 3 to FEP-3.1, Train B Plant Shutdown from Hot Standby to Cold Shutdown Due to Fire ML20153F9341998-03-23023 March 1998 Rev 3 to FEP-2.0, Train a Plant Shutdown to Hot Standby Due to Fire ML20202G6891998-02-0909 February 1998 Proposed Tech Specs Requesting Removal of Table 4.8-1, Diesel Generator Test Schedule & SR 4.8.1.1.3,Repts ML20203H5741998-02-0505 February 1998 Rev 31,change C to EPP-002, Communication & Notification ML20203H5981998-02-0202 February 1998 Rev 3 to EPP-105, Conduct of Drills & Exercises ML20203H5831998-01-27027 January 1998 Rev 5 to EPP-103, Emergency Equipment Checklist ML20153F9461997-10-22022 October 1997 Rev 2 to FEP-2.1, Train a Shutdown from Hot Standby to Cold Shutdown Due to Fire, Change B ML20153F9511997-10-22022 October 1997 Rev 2 to FEP-3.0, Train B Plant Shutdown to Hot Standby Due to Fire, Change B ML20153F9931997-10-22022 October 1997 Rev 2 to FEP-4.0, Control Room Evacuation Due to Fire, Change D ML20210V2481997-06-30030 June 1997 Amend 15 to Training & Qualification Plan ML20217H3521997-06-16016 June 1997 Amend 14 to, Training & Qualification Plan ML20141K2481997-05-21021 May 1997 Proposed Tech Specs Revising Testing Methodology Utilized by VCSNS to Determine Operability of Charcoal Adsorbers in Emergency Safeguards Features Air Handling Units ML20140C1071997-03-26026 March 1997 Proposed Tech Specs Re ECCS Charging/Hhsi Pump Cross Connect & mini-flow Header Isolation Motor Operated Valves ML20140C1401997-03-26026 March 1997 Proposed Tech Specs Re Change to Core Alteration Definition ML20140C0641997-03-26026 March 1997 Proposed Tech Specs 3.8.1.1 Re AC Sources - Operating ML20137F8501997-02-0404 February 1997 Change E,Rev 7 to Inservice Testing of Pumps Second Ten Year Interval RC-96-0229, Startup Report for VC Summer Nuclear Station Power Uprate1996-09-23023 September 1996 Startup Report for VC Summer Nuclear Station Power Uprate ML20138H7191996-09-0606 September 1996 Rev 22 to ODCM for VC Summer Nuclear Station ML20134J9741996-06-0505 June 1996 V C Summer Fuel Assembly Insp Program ML20107G3511996-04-16016 April 1996 Proposed Tech Specs 3/4.6 Re Containment Sys,Per App J, Option B ML20138H7141996-03-25025 March 1996 Rev 21 to ODCM for VC Summer Nuclear Station ML20101E6461996-03-19019 March 1996 Proposed Tech Specs,Consisting of Change Request 95-03, Enhancing LCO & SRs & Revises Bases for QPTR ML20097F4721996-02-10010 February 1996 Proposed Tech Specs,Revising Testing Methodology Utilized to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20096F0211996-01-18018 January 1996 Proposed Tech Specs,Lowering RWCU Isolation Setpoint from Reactor Low Level to Reactor low-low Level ML20095E6541995-12-0808 December 1995 Proposed Tech Specs,Consisting of Change Request 95-07 Re ECCS Pump Testing ML20095A8061995-12-0404 December 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 Correction of Bases 3/4 11-1 ML20094N8881995-11-21021 November 1995 Proposed Tech Specs,Allowing One Time Extension of AOT Specified in TS 3/4.5.2 for Each RHR Train from 72 H to 7 Days ML20094L3531995-11-14014 November 1995 Proposed TS 3/4.8.4.2,removing MOVs Thermal Overload Protection & Bypass Devices ML20094E4111995-11-0101 November 1995 Proposed Tech Specs,Consisting of Change Request 95-01, Permitting VCSNS to Operate at Uprate Power Level of 2900 Mwt Core Power When Unit Restarted After Ninth Refueling Outage ML20093F6131995-08-31031 August 1995 Rev 7 to General Test Procedure (Gtp) GTP-301, IST of Pumps Second Ten Yr Interval ML20092A2371995-08-31031 August 1995 Proposed Tech Specs,Consisting of Change Request TSP 940002, Incorporating Revs to 10CFR20 ML20091L4541995-08-18018 August 1995 Proposed Tech Specs for Uprate Power Operation ML20087F8551995-08-11011 August 1995 Proposed Tech Specs Re Rev to TS Change 95-02 Concerning PORVs & Block Valves ML20087A2601995-07-28028 July 1995 Proposed Tech Specs Re TS 3/4.3.2,ESFAS Instrumentation,Sr 4.3.2.1 Being Revised to Exclude Requirement to Perform Slave Relay Test of 36 Containment Purge Supply & Exhaust Valves on Quarterly Basis While Plant in Modes 1,2,3 or 4 ML20086C0311995-06-30030 June 1995 Proposed Tech Specs Re PORVs & Block Valves ML20085L0411995-06-19019 June 1995 Proposed Tech Specs Re Deletion of Schedular Requirements for Type a Testing ML20085K4591995-06-19019 June 1995 Proposed TS 3/4.6.2, Depressurization & Cooling Sys, Changing Required Test Frequency for Reactor Bldg Spray Nozzle Flow Test from Once Per Five Yrs to Once Per Ten Yrs ML20080K1981995-02-21021 February 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 ML20107L8771995-01-31031 January 1995 Rev 19 to Offsite Dose Calculation Manual ML20078G9231995-01-30030 January 1995 Proposed Tech Specs Re Relocation of Seismic Monitoring Instrumentation 1999-08-19
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Text
,. . . . - . - . . . _ _ . - . . . . . . .~. . - . . - . . . - . . . . . - . .
- N .
ATTACHMENT TO DOCUMENT CONTROL DESK LETTER DATED JULY 8, 1988
" Contents: Paae 3/4-1-11
.3/4 1-12 B 3/4 1-3 Attachment 1, Pages 43, 49 and 51 I
E 1
l 's j$$7300N S 'u ,
, P.
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCE - SHUT 00WN LIMITING CONDITION FOR OPERATION 3.1. 2. 5 As a minimum, one of the following borated water sources shall be OPERABLE:
- a. A boric acid storage system with:
- 1. A minimum can'ained borated water volume of ?i30 gallons, Between 7000 and 7700 ppe of boron, and 2.
- 3. A minimum solution temperature of 65'F.
- b. The refueling water storage tank with: .
- 1. A minimum contained borated water volume of gallons,
, , 2. A minimum boron concentration of 2300 ppe, and
- 3. A minimum solution temperature of 40*F.
APPLICABILITY: MODES 5 cnd 6.
ACTION:
With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1.2.5 The above required borated water source shall be demonstrated OPERABLE: l
- a. At least once per 7 days by:
- 1. Verifying the boron concentration of the water,
- 2. Verifying the contained borated water volume, and
- 3. Verifying the boric acid storage tank solution temperature when it is the source of borated water.
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when it is the source of borated water and the outside air temperature is less than 40*F.
e
- - - - - - sun e - unit 1 __ _ 3/4 A ll . Amendment No. f ___ _
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMI, TING CONDITION FOR OPERATION 3.1.2.6 As a minimum, the following borated water source (s) shall be OPERABLE as required by Specification 3.1.2.2:
- a. A boric acid storage system with:
gg
- 1. A minimum contained borated water volume of.13r200' gallons,
- 2. Between 7000 and 7700 ppa of boron, and
- 3. A minimum solution tev erature of 65'F.
- b. The refueling water storage tank with:
- 1. A minimum contained borated water voltne of 453,800 gallons,
- 2. A minimum boron concentration of 2300 ppe, and
- 3. A minimum solution temperature of 40*F.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
- a. With the boric acid storage system inoperable and being used as one of the above required borated water sources, restore the storage system 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 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 borated to a SHUTDOWN MARGIN equivalent to at least 2 percent delta k/k at 200'F; restore the boric acid storage system to OPERABLE status within the next 7 days 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 />.
- b. With the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANDBY l 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 l 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l l
t l SUPHER - UNIT 1 3/4 1-12 Ame7dme@t NL 61
REACTIVITY CONTROL SYSTEMS
(
!4SES BORATION SYSTEMS (Continued)
MARGIN from expected operating conditions of 1.77% delta k/k or as required by Figure 3.1-3 sfter xenon decay and cooldown to 200*F. The maximum expected boration capability requirement occurs from full power equilibrium xenon condi-tions and is satisfied by G34955 gallons of 7000 ppe borated water from the boric acid storage tanks orQ A egu g s of 2300 ppe borated water from the refuel-ing water storage tank. ( gf,5 l my With the RCS temperature below 200*F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection system becomes inoperable.
~
The limitation for a maximum of one cent;ifugal charging pump to be OPERA 8LE and the Surveillance Requirement to verify all charging pumps except the required OPERA 8LE pump to be inoperable below 275'F provides assurance that a mass addition pressure transient can be relieved by the operation of a 3
single PORV.
l l
^ The boron capability required below 200'F is sufficient to provide the required SHUTDOWN MARGIN of 1 percent delta k/k or as required by Figure 3.1-3 l
after xenon decay and cooldown from 200'F to 140*F. This condition is satisfied by eithe gallons of 7000 ppe borated water from the boric acid storage tanks or gallons of 2300 ppe borated water from the refueling water storage l tank. gg The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.
The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.
3/4.1.3 MOVA8LE CONTROL ASSEMILIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimus SHUTDOWN MARGIN is main-tained, and (3) limit the potential effects of rod misalignment on associated accident analyses. OPERASILITY of the control rod position indicators is
^
required to determine control rod positione and thereby ensure compliance with the control rod alignment and insertion limits.
.s SUM 4ER - UNIT 1 B 3/4 1-3 Amendment No. 61
7.5 Moderator Temperature Coefficient Revisions to the VCSNS Technical Specifications for Maderator Temperature coefficient are proposed.
The BOL limits are increased frca 0 AK/K/'F for the all rods withdrawn (BOL, i
H2P) to +7.0 pcm/*F from HZP to 70% rated power with a negative linear ramp from +7.0 pcm/*F at 70% power to 0.0 pcm/*F at HFP. This change is required due to the increased RCS boron concentrations for VANTAGE 5 and the positive shift in moderator coefficient caused by the larger H/U ratio and small MTV loading for the smaller (empared to LOPAR) VANTAGE 5 fuel rod.
The EOL limits are also increased (more negative) to accommodate longer fuel cycles and extended fuel burnup.
7.6 Borated Water Sources The technical specification requirements for borated water sources during all operating modes were evaluated to determine if current limits remain applicable for the transition to VANTAGE 5 fuel. The bases for the technical ,
specification were preserved by current limit: except for the minimum contained borated water volume in the boric acid storage system during Modes 1-4
~a. A ug waa s+p~p %x d"ung n,Lu 5ud 6.
nau kuauw 4 2L. -rnaum en,+Mw& &
l y L conL%w an. uputut.
7.7 Rod Drop Time The VANTAGE 5 guide thimbles are identical to those in th. LOPsP desijn except for a reduction in the guide thimble diameter and length above the dashpot.
1405v:1D/051688 43
TABLE 7 1 VIRGIL SUMMER TECHNICAL SPECIFICATION CHANGES FOR CYLU 5 RELOAD PAGE SECTION DESCRIPTION OF CHANGE JUSTIFICATION 2-1 2.1.1 Delete reference to two Two loop operation is not loop operation currently licensed 2-2 Figure 2.1-1 Core limits are revised Core limits are revised for Vantage 5 fuel due to ITDP, new peakin6 factors and reduced RCS flow 2-5 Table 2.2-1 Setpoints and nermal Setpoints and TDF are 2-8 Design Flow (TDF) are consistent with the new
- 2-9 changed safety limits, instrtnent 2-10 uncertainty and reduced flow B 2-1 Bases 2.1.1 Discussion of Thennal The analysis is based on and Hydraulic analysis ITDP methodology and the WRB.-1 and -2 correlations B 2-4 Bases 2.2.1 DNBR limit replaced Future changes in analyses by "safety analysis will not require a change DNBR limit" in Bases 3/4 1-3a Figure 3 1-3 Changed shutdown margin This is based on' for Modes 3, 4 and 5 reanalysis of boron dilution with Vantage 5 fuel .
3/4 1-4 3 1.1 3 manged the KTC limits This is based on Vantage 5 fuel 3/4 1-5 4.1.1.3 manged the MTC Limits m is is based on vantage 5 fuel l
3/*/l-fl S. s . 2. 5. tr C% W JU d & en l WN 'S VAdT4c,6 5 lull A l p RWs7 4fM f.
3/4 1-12 3 1.2.6.a Changed minimtn borated n is is based on vantage 5 i water voltne for boric fuel and extended fuel acid system cycles 3/4 1-19 3 1 3.4 Changed rod drop time m is is based on Vantage 5 fuel 3/4 2 1, 3 2.1 manged AFD requirements This is based on Vantage 5 3/4 2-2, fuel, RAOC and base load 3/4 2-3 operation
, 49 1
L_
~
TABLE 7.1 VIRGIL SUPER TECHNICAL SPECIFICATION CHANGES FOR CYCLE 5 RELOAD
, PAGE SECTION DESCRIPTION OF CHANGE JUSTIFICATION 3/45-6 4.5.2 Changed charging pmp his is based on the flow balance limit to revised safety analyses, reflect testing with where the charging pmp recirculation recirculation was not isolated during the accidents 3/4 10-2 4.10.2.2 m anged surveillance Reflects correct section n ebers to specification r'nbers reflect use of FQ as for N surveillance opposed tJ Fxy surveillance B 3/4 1-2 3/4 1.1 3 Changed MrC limits This is based on Vantage 5 fuel B 3/4 1-3 3/4.1.2 manged boration volmes TM y/dw e b+%hnuM p w U B 3/4 2-1 3/4.2, 3/4.2.1, Change d F(Q), DNB limit, h is is based on optimized B 3/4 2-2 3/4.2.2 and deleted Fxy, and revised selection of parameters, B 3/4 2-3 '
3/4.2 3 discussion of AFD Vantage 5 fuel, ITDP, B 3/4 2-4 RAOC and baseload l B 3/4 2-5 operation l
B 3/4 5-1 3/4.5.1 Added ccament for borated The acetnulators are water and secondary pipe actuated in the steam ruptures line break ana'.ysis l
I 6-18 6.9.1.11 Change discussion of h is is based on Vantage 5 peaking factor report fuel, RAOC and base load l operation. The approved methodology is referenced 51
-