Proposed Tech Specs Deleting Section 3/4.5.4, Boron Injection Sys, Modifying Bases Section B3/4.5.5, Refueling Water Storage Tank & Incorporating Necessary Changes to IndexML20113D443 |
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Summer ![South Carolina Electric & Gas Company icon.png](/w/images/6/6b/South_Carolina_Electric_%26_Gas_Company_icon.png) |
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04/09/1985 |
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SOUTH CAROLINA ELECTRIC & GAS CO. |
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ML20113D431 |
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NUDOCS 8504150296 |
Download: ML20113D443 (10) |
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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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ATTACHMENT A TECHNICAL SPECIFICATION CHANGES B504150296 DR 850409 ADOCK 05000395 PDR
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INDEX Ii LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS............................................. 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,yg >350*F........................... 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,yg <350*F........................... 3/4 5-7
- t # P MMMMLt PVPT wi ,A. w . ,A wwnwn . nv Ti.v Ll i f f*T. .T.nMk1 w . w .wEM.
es - - - - _ *_1 _A * =r _ _ a _
- 1 / A E_n UU5 U55 AliJ Wh b 4 UIB 5E5533%..................................... wp T w w U__A T___f__ 9 #A E_9A s ssu b g5uh4sg............................................. d/ "T d ekW l 3/4.5./ REFUELING WATER STORAGE TANK.............................
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I SIM4ER-UNIT 1 VI
INDEX p BASES SECTION PAGE 3/4.4.6 STEAM GENERATORS.......................................... B 3/4 4-3 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE............................ B 3/4 4-4 3/4.4.8 CHEMISTRY................................................. B 3/4 4-5 3/4.4.9 SPECIFIC ACTIVITY......................................... B 3/4 4-5 3/4.4.10 PRESSURE / TEMPERATURE LIMITS............................... B 3/4 4-6 3/4. 4. n STRUCTURAL INTEGRITY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-15 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS.............................................. B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS............................... B 3/4 5-1 3/4.5.4 00:0M : = CTION SYST01.................................... : /4 ;-2
( 4 B 3/4 5-2 3/4.5.5 REFUELING WATER STORAGE TANK ............................
3/4.6 CONTAIMENT SYSTEMS 3/4.6.1 PRIMARY C0NTAIMENT. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND C00Lhh SYSTEMS. . . . . . . . . . . . . . . . . . . . . . B 3 3/4.6.3 PARTICULATE IODIME CLEANUP SYSTEM......................... B 3/4 6-4 3/4.6.4 CONTAIMENT ISOLATION VALVES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-5 3/4.6.5 ComuSTIB LE GAS CONTR0L. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-5 l
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( SUMER-UNIT 1 XIII l
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EMERGENCY CORE COOLING SYSTEMS 4.5.4 BORON INJECTION SYSTEM BORM INJECTION TANK LIMIT ONDITION FOR OPERATION 3.5.4.1 The ron injection tank shall be OPERABLE with:
- a. A min um contained borated water volume of 900 gall ns,
' b. A boron ncentration of between 20,000 and 22,50 ppm, and
- c. A minimum s ution temperature of 145'F.
APPLICABILITY: MODES 1, and 3.
ACTION:
With the boron injection tank 1 operable, resto the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in HOT STAN Y and borate to a SHUTDOWN MARGIN equivalent to 2% delta k/k at 200*F within t e next 6 urs; restore the tank to OPERABLE status within the next 7 days or b in HOT HUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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SURVEILLANCE REQUIREMENTS l l
i 4.5.4.1 The boron injecti tank shall be demon rated OPERABLE by: !
- a. Verifying th ontained borated water vol at least once per 7 1 days, l
1
- b. Verifyi the boron concentration of the water the tank at least once p 7 days, and
- c. Ver' ying the water temperature at least once per 24 ours.
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SUMMER - UNIT 1 3/4 5-9 w- -- -- - , +
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\fMERGENCY CORE COOLING SYSTEMS H T TRACING @IM l
LIMIT G CONDITION FOR OPERATION
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l 3.5.4.2 At least two independent channels of heat tracing shall e OPERABLE for the boro injection tank and for the heat traced portions the associ-ated flow path .
APPLICABILITY: DES 1, 2 and 3.
ACTION:
With only one channel heat tracing on either th boron injectica tank or on the heat traced portion f an associated flow pat OPERABLE, operation may continue for up to 30 day provided the tank and flow path temperatures are verified to be greater than r equal to 145*F a least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; otherwise, be in at least HO STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS E \
4.5.4.2 Each heat tracing ch nel for the boro injection tank and associated flow path shall be demonstra ed OPERABLE:
- a. At least once p 31 days by energizing e h heat tre .ng channel, and
- b. At least on per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the ta and flow path temperatur to be greater than or equal to 145 The tank temperat e shall be determined by measurement. e flow path tempera re shall be determined by either measureme t or recircula-tion f ow until establishment of equilibrium tempera res within the tank i
4 4
SUMMER - UNIT 1 3/4 5-10
. - _ . - - . - . - . _ _ - . - . . _ . . _ _ _ . - - . _ . , - - - . . - , = . -. - ,- - _- - .... - .-, - - - .,
EMERGENCY CORE COOLING SYSTEMS 3/4.5. REFUELING WATER STORAGE TANK c
LIMITING CONDITION FOR OPERATION 3.5.5 The refueling water storage tank (RWST) shall be OPERABLE with:
- a. A minimum contained borated water volume of 453,800 gallons,
- b. A boron concentration of between 2000 and 2100 ppm of boron, and
- c. A minimum water temperature of 40'F.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With the refueling water storage tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within 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 />.
ef
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SURVEILLANCE REQUIREMENTS 4.5.5 The RWST shall be demonstrated OPERABLE:
- a. At least once per 7 days. bye
- 1. Verifying the contained borated water volume in the tank, and
- 2. Verifying the boron concentration of the 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 the outside air temperature is less than 40*F.
g SUMMER - UNIT 1 I 3/45-)9
EMERGENCY CORE COOLING SYSTEMS
{
BASES ECCS SUBSYSTEMS (Continued)
The limitation for a' maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE charging punis to be inoperable below 300*F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
(
'3M. 4 BORON INJECTION SYSTEM 'DR ET6 The 0 ILITY of the boron injection system as part of the ensures that sufficien ative reactivity is injected into the core counteract any positive increa n reactivity caused by RCS system down. RCS cooldown can be caused by inadver t depressurization, a lo -coolant accident or a steam line rupture. '
The limits on injection tank mi contained volume and boron concentration ensure that the as tions in the steam line break analysis are met. The contained wat olume limit inc an allowance for water not usable because of tank charge line location or o physical characteristics.
The OPE ITY of the redundant heat tracing channels ciated with the bor njection system ensure that the solubility of the boro lution wi e maintained above the solubility limit of 135'F at 22,500 ppe .
!- 3/4.5. REFUELING WATER STORAGE TANK The OPERABILITY of the Refueling Water Storage Tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection i by the ECCS in the event of a LOCA. The limits on RWST minimum volume and -
' boron concentration ensure that 1) sufficient water is available within contain-ment to permit recirculation cooling flow to the core, and 2) the reactor will
, remain subcritical in the cold condition following mixing of the RWST and the L
SU M ER - UNIT 1 B 3/4 5-2
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EMERGENCY CORE COOLING SYSTEMS
(.
BASES REFUELING WATER STORAGE TANK (Continued)
RCS water volumes with all control rods inserted except for the most reactive control assembly. These assumptions are consistent with the LOCA analyses.
I ' The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
!1 1
Etba.N NA 6(M8 i
AAAh4 the OPERABILITY of the 5:= 3jectier :[f d=UM as part of the ECCS ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS system cooldown. RCS cooldown can be caused by inadvertent depressurization, a loss-of-coolant accide~nt or a steam line rupture. - - - -
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SUPMER - UNIT -1 B 3/4 5-3
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Attachment B No Significant Hazards Determination 1.)- Is the probability of, occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated significantly-increased? NO.
There is no increase in the probability of an accident occurrence above that previously evaluated due to the removal of the BIT.
Equipment removal and minor SI piping rerouting do not increase the likelihood of accidents. Fire protection analysis is not inpacted, however fire sources in the plant are reduced since equipment which is a potential fire source is removed.
There is no increase in the consequence of an accident previously evaluated due to.the removal of the BIT. Accident analysis has demonstrated that the containment environmental conditions (pressure / temperature) are not above that previously generated for the main steam line break. DNBR has been demonstrated to remain above the 10 CFR limit of 1.30. Failed fuel quantities are unchanged; therefore,10 CFR100 criteria are still satisfied. Pipe rupture analysis has demonstrated that new postulated pipe mptures do not affect the ability to safely shutdown the plant.
There is no increase in the probability of malfunction of equipment important to safety previously evaluated due to the removal of the BIT. The main steam line break analysis has demonstrated that the containment environmental conditions (pressures / temperature) are not above that previously generated. Therefore, equipment inportant to safety will still perform necessary functions to mitigate the consequences of the accident. Pipe mpture analysis demonstrates that equipment important to safety is not compromised. The likelihood of fire is _not increased and therefore will not have an inpact on-equipment .important to safety.
Radioactive releases due to the main steam line break are bounded by FSAR 15.4 analysis since postulated fuel f ailure has not changed from
- original licensing analysis (Source term does not change.)
2.) Is 'a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report created? N0.
There is no creation of a different type of accident or malfunction beyond those previously evaluated due to the removal of the BIT.
No new radioactive material release paths, and no new fire hazards are
- created by removal of the BIT. Actually, removal of the BIT eliminates heat tracing which is a potential fire hazard and also eliminates the BIT safety relief valve which is potential radioactive material release path.
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3.) Is the margin of safety as defined in the basis for any technical specification significantly reduced? NO.
- There are no reduced safety margins as defined in Technical Specifications bases due to removal of the BIT. Reactor core analysis has demonstrated that~ the pressure / temperature response is less severe
- than the results obtained in the plant licensing analysis. Safety margins for. pipe nJpture/ jet inpingement, radioactive material release, equipment qualification, and fire hazards are not adversely affected by the removal of the BIT.