|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 ML20078P8251995-02-10010 February 1995 Proposed Tech Specs 2.10 to Relocate Requirements for Incore Instrumentation Sys ML20077S1691995-01-0909 January 1995 Proposed Tech Specs,Reflecting Deletion of Requirements for Toxic Gas Monitoring Sys ML20078G8981994-11-11011 November 1994 Proposed Tech Specs 5.2 & 5.5,reflecting Administrative Changes ML20024J3921994-10-0707 October 1994 Proposed Tech Specs,Deleting SRs in TS 3.6(3)a for Eight Raw Water Backup Valves to Containment Cooling Coils,Deleting SRs in TS 3.2,Table 3-5,item 6 for 58 Raw Water Valves & Revising Basis of TS 2.4 to Reflect Changes ML20069H9261994-06-0606 June 1994 Proposed Tech Specs Incorporating Changes to Credit Leak Before Break Methodology to Resolve USI A-2, Asymmetrical Blowdown Loads on Rcps ML20069D8451994-05-25025 May 1994 Proposed Tech Specs Requesting one-time Schedular Exemption from 10CFR50.36a(2) ML20062N4211993-12-28028 December 1993 Proposed TS Tables 3-1 & 3-2 Re Min Frequencies for Checks, Calibrs & Testing of RPS & Min Frequencies for Checks, Calibrs & Testing of ESFs & Instrumentation & Controls, Respectively LIC-93-0228, Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys1993-08-20020 August 1993 Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys ML20045H1791993-07-12012 July 1993 Proposed TS 2.14,Table 2-1,Item 6.b Re ESF Sys Initiation, Degraded Voltage Setting Limits LIC-93-0159, Proposed Tech Specs Incorporating Administrative Changes1993-06-17017 June 1993 Proposed Tech Specs Incorporating Administrative Changes ML20128E5341993-02-0808 February 1993 Proposed Tech Specs Deleting Section 5.9.4 Re Radioactive Effluent Release Rept.Draft Chemistry Manual Procedure Encl ML20128C0461993-02-0101 February 1993 Proposed TS Figures 2-1A & 2-1B Re pressure-temp Limits for Heatup & Cooldown,Respectively 1999-05-26
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR LIC-98-0141, SG Eddy Current Test Rept for 1998 Refueling Outage. with1998-10-27027 October 1998 SG Eddy Current Test Rept for 1998 Refueling Outage. with ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20211N7591997-10-0202 October 1997 Rev 0 to Fort Calhoun Station Unit 1 Operating Instruction, OI-ES-3, Engineered Safeguard Controls Normal Mode 1,2 & 3 Alignment Check ML20211N7521997-09-21021 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-04, Annunciator Marking ML20211N7471997-09-12012 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-08, Plastic Label Usage ML20211N7661997-08-25025 August 1997 Rev 4 to Fort Calhoun Station Unit 1 Annunciator Response Procedure ARP-1, APR-1 Annunciator Response Procedure ML20211N7411997-08-24024 August 1997 Rev 0 to Fort Calhoun Operations Dept Policy & Directive OPD-5-14, Test Monitor Program ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134J6841997-01-20020 January 1997 Rev 5,Change a to Security Training & Qualification Program LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20129C5351996-03-0101 March 1996 Rev 0 to Incore Instrumentation Operability Requirements ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20108A7161995-12-19019 December 1995 Rev 7 to CH-ODCM-0001, ODCM, Incorporating TS Amend 171 for Section 3.1 Update/Reflect Changing Environ ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20091P4011995-09-0101 September 1995 Rev 3 to Fort Calhoun Station ISI Program Plan Third Ten-Yr Interval 1993-2003 ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20085M0081995-06-15015 June 1995 Rev 2 to ISI Program Plan for 1993-2003 Interval ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20108A7121995-03-15015 March 1995 Rev 6 to CH-ODCM-0001, ODCM, Incorporating New TS Amend 164 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 1999-05-26
[Table view] |
Text
-
i TABLE 3-4 (Continued)
MINIMUM FRE0VENCIES FOR SAMPLING TEST Type of Measurement Sample and Analysis and Analysis .Freauency
- l. Reactor Coolant (Continued)
(c) Cold Shutdown (1) Chloride I per 3 days (Operating Mode 4)
(d) Refueling Shutdown (1) Chloride 1 per 3 days (3)
(Operating Mode 5) (2) Boron Concentration 1 per 3 days (3)
(e) Refueling Operation (1) Chloride 1 per 3 days (3)
(2) Boron Concentration 1 per shift (3)
- 2. SIRW Tank Boron Concentration 1 per 31 days
- 3. Concentrated Boric Acid Boron Concentration 1 per 31 days l Tanks
- 4. SI Tanks Boron Concentration 1 per 31 days
- 5. Spent Fuel Pool Boron Concentration 1 per 31 days (1) Until the radioactivity of the reactor coolant is restored to s 1 Ci/gm DOSE EQUIVALENT I-131.
(2) Sample to be taken after a minimum of 2 EFPD and 20 days of power operation have elapsed since reactor was suberitical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
(3) Boron and Chloride sampling / analyses are not required when the core has been off-loaded. Reinitate boron and chloride sampling / analyses one
- shift prior to reloading fuel into the cavity to assure adequate shutdown margin and allowable chloride levels are met, i:
l l
l l 3-19 ggr488s! te83Er P
l
. ~
nab- e a e s.saa -,n.-w-- -- - -- - - , - -
I ., .
?
<g .,
a ,
e a ' i e ,
n iGF-I a
t f
6
.I i
I ':
1 1'
t ATTACHMENT B 1 1
F t
t i
F e
+
9
?
m D.LSCUSSION OF CHANGE The proposed amendment to the Technical Spocification allows for suspension of boron and chloride sampling in the reactor vessel when all fuel has been removed. Sampling will be reinitiated arior to reintroduction of the fuel into !
the reactor vessel to insure adequate slutdown margin and chloride chemistry l 1evels are met. '
Suspension of boron and chloride sampling of the reactor vessel coolant when all fuel is removed will not affect the plant safety since no fuel is present.
The reactor vessel coolant boron concentration requirement is based on the need for adequate shutdown margin when fuel it pensent. When all the fuel is removed, the need for boron is eliminated and hence the need for sampling is eliminated. Elimination of the sampling requirement for the reactor vessel head removal will not adversely impact the safe speration since the shutdown margin calculations do not credit the CEA's. The' intent of the reactor vessel head removal would be to ensure CEA's were not inadvertently withdrawn causing a criticality excursion, however since the refueling shutdown calculations include an all rods out assumption, then the deletion of the boron shift sampling requirements will not change the safety analyses.
The deletion of the chloride samaling will not adversely impact the fuel since the purpose of maintaining the c11oride chemistry level is to meet warranty obligations of the fuel vendor and reduce the possibility of intergranular stress corrosion cracking in the fuel assembly material. The chloride chemistry level is established to prevent any potential degradation of the fuel mechanical design properties or RCS piping. The chloride chemistry level of the fuel assemblies is met by sampling of the Spent fuel pool.
@STIFICATION The suspension of reactor vessel coolant boron sampling or chloride sampling when all fuel is removed from the vessel does not compromise or affect the safety of the plant operation.
NO SIGNlflCANT HAZARDS The proposed amendment to the Technical Specification allows for suspension of boron and chloride sampling in the reactor vessel when O' fuel has been removed, The Technical Specification document changes required are contained in pages 2-37, 2-38, and 3-19 of Sections 2.8 and 3.2.
The reactor vessel coolant boron concentration requirement is based on the need "
for adequate shutdown margin when fuel is present. When all the fuel is removed, the need for boron is eliminated and hence the need for sampling is eliminated. Elimination of the sampling requirement for the reactor vessel head removal will not adversely impact the safe operation since the shutdown !
margin calculations do not credit the CEAs. The intent of the reactor vessel head removal would be to ensure CEAs were not iradvertently withdrawn causing a
, criticality excursion, however since the refuelSg shutdown calculations include an all rods out assumption, then the deletion of the boron shift sampling requirements will not change the safety analyses. ;
l-L I
The deletion of the chloride sampling will not adversely impact the fuel since the purpose of maintaining the chloride chemistry level is to meet warranty obligations of the fuel vendor and reduce the possibility of intergranular stress corrosion cracking in the fuel assembly material. The chloride chemistry level mechanical is established design properties orto prevent RCS anyTh.otential piping. c chloridedegradation of theoffuel chemistry icvel the fuel assemblies is met by sampling of the Spent Fuel Fool.
BAS 15 FOR NO SIGNIFICANT HAZARDS DETERMINATION This proposed amendment does not involve a significant hazards consideration because the operation of Fort Calhoun Station in accordance with this amendment would not:
)
- 1) Involve a significant increase in the arobability or consequences of an i accident previously evaluated. This c1ange allows for the suspension of boron and chloride sampling during the time the fuel is removed from the reactor vessel with no changes in specifications. Since the fuel source is removed, shutdown margin in the reactor vessel is not required and hence boron sampling is not required and the mechanical design properties of the fuel or RCS piping are not subject to potential degradation due to intergranular stress corrosion cracking potentially induced by a high chloride level. Therefore, this change does not increase the probability or consequences of a previously evaluated accident.
- 2) Create the possibility of a new or different kind of accident from any l accident previously evaluated, it has been determined that a new or different kind of accident is not created because no new or different modes of operation are proposed for the plant. The use of the proposed revised Technical Specification controls will not result in the possibility of a l new or different kind of accident. '
- 3) Involve a significant reduction in a margin of safety. Specifications involving the boron sampling ensure that the shutdown margin conforms to current plant conditions and, therefore, preserves the margin of safety.
Since the fuel source is removed, shutdown margin in the reactor vessel is not required and hence boron sampling is not required. The fuel manufacturer's chloride chemistry requirements are set by sampling of the S)ent Fuel pool during the period the core is offloaded. This maintains a tie mechanical design properties of the fuel. Consolidation of all the !
boron and chloride sampling requirements in one location in the Technical l Specifications ensures compliance of sampling requirements and, therefore, will not reduce the margin of safety.
Based on the above considerations, OPPD does not believe that this amendment involves a significant hazards consideration.
4