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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20195B4371999-05-26026 May 1999 Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure- Temp Limits Rept ML20205J7631999-03-31031 March 1999 Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate ML20203A0991999-01-29029 January 1999 Application for Amend to License DPR-40,relocating Three cycle-specific Parameter Limits from FCS TS to COLR ML20195K1771998-11-17017 November 1998 Revised Application for Amend to License DPR-40, Incorporating Addl Restrictions on Operation of MSSVs ML20154A0661998-09-28028 September 1998 Application for Amend to License DPR-40,allowing Installation of Capability for Override of Containment Isolation Actuation Signal Closure Signal to Containment Isolation Valves for RCS Letdown Flow ML20217B8181998-03-18018 March 1998 Application for Amend to License DPR-40,requesting Tech Specs Set Forth in App a to License Amended to Clearly Address Regulatory Requirements for Alternate Shutdown Panel & Auxiliary Feedwater Panel ML20217B8481998-03-18018 March 1998 Application for Amend to License DPR-40,changing TS 5.2 & 5.11.2 to Change Title of Shift Supervisor to Shift Manager ML20217P1981998-03-0303 March 1998 Application for Amend to License DPR-40,revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L8911998-01-30030 January 1998 Application for Amend to License DPR-40,relocating pressure- Temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept (PTLR) ML20199L7221998-01-30030 January 1998 Application for Amend to License DPR-40,requesting Deletion of Section 3.E, License Term from License ML20203G4101997-12-11011 December 1997 Application for Amend to License DPR-40,adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1221997-11-21021 November 1997 Application for Amend to License DPR-40,revising Tech Specs 5.19 by Incorporating Editoral Changes & Two Exceptions to NEI-94-01,Rev 0, Industry Guideline for Implementing Performance-Based Option of 10CFR50,App J ML20217G4541997-10-0303 October 1997 Application for Amend to License DPR-40,revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20196J0781997-07-25025 July 1997 Application for Amend to License DPR-40,allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance & Implementing Option B of 10CFR50,App J ML20137Y1591997-04-17017 April 1997 Application for Amend to License DPR-40,requesting Rev to Administrative Controls Consistent w/NUREG-1432 Standard TS for Combustion Engineering Plants.Tech Specs Encl LIC-97-0049, Application for Amend to License DPR-40,incorporating Addl Restrictions on Operation of MSSVs1997-03-26026 March 1997 Application for Amend to License DPR-40,incorporating Addl Restrictions on Operation of MSSVs ML20138L4341997-02-20020 February 1997 Application for Amend to License DPR-40,requesting to Update TS Re Rev to Position Titles & Relocation of Controls for Personnel Working Hours ML20134N8491996-11-20020 November 1996 Application for Amend to License DPR-40,requesting Administrative Revisions to Paragraph 3,Table of Contents, Tech Spec 2.15 & Section 5 of Appendix a ML20129E4921996-10-24024 October 1996 Application for Amend to License DPR-40,TS 4.3.2, Reactor Core & Control, Allowing Use of Either Zircaloy or ZIRLO Cladding ML20129C2491996-10-22022 October 1996 Application for Amend to License DPR-40,revising TS 4.3.2, Reactor Core & Control & Adding Ref to WCAP-12610 in TS 5.9.5b ML20117B8771996-08-23023 August 1996 Application for Amend to OL Revising Paragraph 2.B of License to Allow Use of Source Matl as Reactor Fuel ML20115F9971996-07-15015 July 1996 Application for Amend to License DPR-40,revising Description of Reactor Core & Control & Adding Westinghouse Topical Rept List of Analytical Methods,Used to Determine Core Operating Limits ML20112D3151996-05-31031 May 1996 Application for Amend to License DPR-40,adding LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6951996-05-20020 May 1996 Application for Amend to License DPR-40,clarifying Surveillance Test Requirements in TS 3,1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5871996-05-17017 May 1996 Application for Amend to License DPR-40,relocating Operability Requirements for Shock Suppressors (Snubbers) from TS to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20097C3031996-02-0101 February 1996 Application for Amend to License DPR-40,allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool ML20100C0161996-01-22022 January 1996 Application for Amend to License DPR-40 Revising TS Re Requirement for Placing Sirw Tank low-level Channels in Bypass Rather than Trip ML20094N8571995-11-16016 November 1995 Application for Amend to License DPR-40,adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses LIC-95-0167, Application for Amend to License DPR-40,revising TS 2.7 Extending Allowed Outage Time from 7 Days Per Month to 7 Days W/Addl Once Per Cycle 10 Day Allowed Outage Time1995-09-0606 September 1995 Application for Amend to License DPR-40,revising TS 2.7 Extending Allowed Outage Time from 7 Days Per Month to 7 Days W/Addl Once Per Cycle 10 Day Allowed Outage Time ML20087E0241995-08-0404 August 1995 Application for Amend to License DPR-40,revising TS Re Reducing Min Operable Containment Radiation High Signal Channels ML20086L5921995-07-11011 July 1995 Application for Amend to License DPR-40,proposing TS Allowing Up to 24 Hours to Resotre SIT Operability If Inoperable ML20091G3651995-06-27027 June 1995 Application for Amend to License DPR-40.Amend Would Extend Allowed Outage Time for Inoperable LPSI Pump from 24 H to Seven Days ML20086D3601995-06-27027 June 1995 Application for Amend to License DPR-40.Amend Will Modify & Reformat TS Re Chemical & Vol Control Sys ML20084G7721995-05-31031 May 1995 Application for Amend to License DPR-40 to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0021995-05-0808 May 1995 Application for Amend to License DPR-40,incorporating Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20082J0811995-04-0707 April 1995 Application for Amend to License DPR-40.Amend Would Incorporate Administrative Changes ML20087G9651995-04-0707 April 1995 Application for Amend to License DPR-40.Amend Would Relocate Axial Power Distribution Figure from TSs to Core Operating Limits Rept ML20080T9001995-03-0101 March 1995 Application for Amend to License DPR-40,incorporating Administrative Revs to TS 5.5 & 5.8,per GL 93-07, Mod of TS Administrative Control Requirements for Emergency & Security Plans & Revs Unrelated to GL to TS 2.5,2.8,2.11,3.2 & 3.10 ML20078P8191995-02-10010 February 1995 Application for Amend to License DPR-40,revising TS to Relocate Requirements for Incore Instrumentation Sys ML20077S1541995-01-0909 January 1995 Application for Amend to License DPR-40,revising Specs 2.22 & 3.1 to Delete Requirements for Toxic Gas Monitoring Sys ML20078G8951994-11-11011 November 1994 Application for Amend to License DPR-40,making Administrative Changes to TSs 5.2 & 5.5 ML20024J3911994-10-0707 October 1994 Application for Amend to License DPR-40,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 ML20069H9061994-06-0606 June 1994 Application for Amend to License DPR-40,revising Ts,By Incorporating Changes to Credit Leak Before Break Methodology to Resolve USI A-2, Asymmetrical Blowdown Loads on Rpcs ML20069D8401994-05-25025 May 1994 Application for Amend to License DPR-40,requesting one-time Schedular Exemption from 10CFR50.36a(2) ML20062N4171993-12-28028 December 1993 Application for Amend to License DPR-40,revising TS Surveillance Test Frequency from Monthly to Quarterly for Several Channel Functional Tests for RPS & ESF Instrumentation & Controls ML20057F7191993-10-11011 October 1993 Application for Amend to License DPR-40,proposing Changes to TS 5.9.5 Deleting Revision Numbers & Dates of Core Reload Analysis Methodology Topical Reports ML20057B6891993-09-17017 September 1993 Application for Amend to License DPR-40,revising Spec 2.7 to Enable Current Configuration of Fuel Oil Sys for EDGs to Meet Capacity Requirements of IEEE-308,providing Fuel for 7 Days of DG Operation Following Most Limiting Accident ML20057B8101993-09-15015 September 1993 Application for Amend to License DPR-40,requesting TS in Appendix a Be Amended to Implement Changes That Move Fire Protection Requirements from TS Into USAR in Accordance W/Gl 86-10 & GL 88-12 ML20057A8941993-09-10010 September 1993 Application for Amend to License DPR-40,revising TS Section 5.9,5.11 & 5.16 to Reflect New 10CFR20 & Administrative Changes ML20056F4071993-08-20020 August 1993 Application for Amend to License DPR-40,incorporating Changes to Credit Leak Before Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys 1999-05-26
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217B5201999-10-0606 October 1999 Amend 193 to License DPR-40,revising TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance Requirements for RCS Flow Rate ML20211L3441999-09-0202 September 1999 Corrected Tech Spec Page 2-50 to Amend 192 to License DPR-40.Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) ML20210G2131999-07-27027 July 1999 Amend 192 to License DPR-40,revising TS Sections 2.2 & 2.10. 2 to Relocate 3 cycle-specific Parameters to Core Operating Limits Repts ML20210D9861999-07-22022 July 1999 Amend 191 to License DPR-40,authorizing Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation Actuation Signal Closure Signal to Reactor Coolant Sys ML20195B4371999-05-26026 May 1999 Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure- Temp Limits Rept ML20205Q5791999-04-15015 April 1999 Amend 190 to License DPR-40,revising TS 5.2.f & TS 5.11.2 to Change Title of Shift Supervisor to Shift Manager ML20205J7631999-03-31031 March 1999 Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate ML20207E9761999-03-0303 March 1999 Errata to Amend 188 to License DPR-40,correcting Incorrect Page Number,Missing Parenthesis & Misspelled Word ML20203A0991999-01-29029 January 1999 Application for Amend to License DPR-40,relocating Three cycle-specific Parameter Limits from FCS TS to COLR ML20198S4611998-12-31031 December 1998 Amend 188 to License DPR-40,revising TS 2.12, Control Room Sys, to Delete Limiting Condition for Operation & Surveillance for Control Room Temp ML20198S3731998-12-31031 December 1998 Amend 189 to License DPR-40,revising TS 2.1.6 to Restrict Number of Inoperable Main Steam Safety Valves When Reactor Critical & Revising Associated Basis ML20195K1771998-11-17017 November 1998 Revised Application for Amend to License DPR-40, Incorporating Addl Restrictions on Operation of MSSVs ML20154N2361998-10-19019 October 1998 Amend 187 to License DPR-40,revising TS 3.9 to Clarify Required Flow Paths for Auxiliary Feedwater Sys & Deleting Surveillance Requirement for Specific Auxiliary Feedwater Pump Discharge Pressure ML20154M4841998-10-19019 October 1998 Amend 186 to License DPR-40,revising TS 2.3 to Increase Allowed Outage Times for SIT ML20154A0661998-09-28028 September 1998 Application for Amend to License DPR-40,allowing Installation of Capability for Override of Containment Isolation Actuation Signal Closure Signal to Containment Isolation Valves for RCS Letdown Flow ML20217L0521998-03-23023 March 1998 Amend 185 to License DPR-40,revising TS to Implement 10CFR50,App J,Option B & to Allow Performance Based Changes in Conducting ILRT & Local Leak Rate Testing Types B & C & SER ML20217B8481998-03-18018 March 1998 Application for Amend to License DPR-40,changing TS 5.2 & 5.11.2 to Change Title of Shift Supervisor to Shift Manager ML20217B8181998-03-18018 March 1998 Application for Amend to License DPR-40,requesting Tech Specs Set Forth in App a to License Amended to Clearly Address Regulatory Requirements for Alternate Shutdown Panel & Auxiliary Feedwater Panel ML20217P1981998-03-0303 March 1998 Application for Amend to License DPR-40,revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20203M4121998-02-0303 February 1998 Amend 184 to License DPR-40,revising TS to Reflect Administrative Changes ML20199L7221998-01-30030 January 1998 Application for Amend to License DPR-40,requesting Deletion of Section 3.E, License Term from License ML20199L8911998-01-30030 January 1998 Application for Amend to License DPR-40,relocating pressure- Temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept (PTLR) ML20203A4131998-01-26026 January 1998 Amend 183 to License DPR-40,revises TS to Delete Requirements for Toxic Gas Monitoring Sys Contained in TS 2.22 & TS 3.1,table 3-3,item 29,for Toxic Chemicals Except Ammonia ML20203G4101997-12-11011 December 1997 Application for Amend to License DPR-40,adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20203E0171997-12-10010 December 1997 Corrected TS Pages 3-7 & 3-12 to Amend 182 to License DPR-40,adding Words That Were Omitted from TS Pages ML20199L0441997-11-24024 November 1997 Amend 182 to License DPR-40,revising TSs to Correct & Clarify Several Surveillance Test Requirements for Reactor Protection Sys & Other Plant Instrumentation & Control Sys ML20199K1221997-11-21021 November 1997 Application for Amend to License DPR-40,revising Tech Specs 5.19 by Incorporating Editoral Changes & Two Exceptions to NEI-94-01,Rev 0, Industry Guideline for Implementing Performance-Based Option of 10CFR50,App J ML20217G4541997-10-0303 October 1997 Application for Amend to License DPR-40,revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20196J0781997-07-25025 July 1997 Application for Amend to License DPR-40,allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance & Implementing Option B of 10CFR50,App J ML20137Y1591997-04-17017 April 1997 Application for Amend to License DPR-40,requesting Rev to Administrative Controls Consistent w/NUREG-1432 Standard TS for Combustion Engineering Plants.Tech Specs Encl ML20137L6121997-03-27027 March 1997 Amend 181 to License DPR-40,revising Section 5.2 of TS to Relocate Controls for Working Hours to Updated Safety Analysis Rept LIC-97-0049, Application for Amend to License DPR-40,incorporating Addl Restrictions on Operation of MSSVs1997-03-26026 March 1997 Application for Amend to License DPR-40,incorporating Addl Restrictions on Operation of MSSVs ML20138L4341997-02-20020 February 1997 Application for Amend to License DPR-40,requesting to Update TS Re Rev to Position Titles & Relocation of Controls for Personnel Working Hours ML20134N7651997-02-13013 February 1997 Amend 180 to License DPR-40,revises TS to Add Limiting Condition for Operation & Surveillance Test for Safety Related Inverters & Deletes Nonsafety Related Instrument Buses ML20133M6641997-01-15015 January 1997 Errata to Amend 179 to License DPR-40,revising Page 2-22 Which Incorrectly Stated Amount of Active TSP That Shall Be Contained in TSP Baskets ML20133C2741996-12-30030 December 1996 Amend 179 to License DPR-40,revising TSs to Increase Amount of TSP Dodecahydrate Located in Containment Sump Storage Baskets ML20134N8491996-11-20020 November 1996 Application for Amend to License DPR-40,requesting Administrative Revisions to Paragraph 3,Table of Contents, Tech Spec 2.15 & Section 5 of Appendix a ML20129H3261996-10-25025 October 1996 Amend 178 to License DPR-40,changing Section 4.3.2 of TS to Allow Use of Zircaloy or ZIRLO Fuel Cladding & to Use Depleted U as Reactor Fuel Matl ML20129E4921996-10-24024 October 1996 Application for Amend to License DPR-40,TS 4.3.2, Reactor Core & Control, Allowing Use of Either Zircaloy or ZIRLO Cladding ML20129C2491996-10-22022 October 1996 Application for Amend to License DPR-40,revising TS 4.3.2, Reactor Core & Control & Adding Ref to WCAP-12610 in TS 5.9.5b ML20128F6251996-10-0202 October 1996 Amend 177 to License DPR-40,modifying Paragraph 2.B.(2) W/Ref to 10CFR40 Allowing Use of Source Matl,In Form of Depleted or Natural U,As Reactor Fuel ML20129G2911996-09-27027 September 1996 Amend 176 to License DPR-40,revising Sections 2.18,3.14, 3.3 & 5.10 of TS to Relocate Snubber Operability Requirements to USAR ML20117B8771996-08-23023 August 1996 Application for Amend to OL Revising Paragraph 2.B of License to Allow Use of Source Matl as Reactor Fuel ML20115F9971996-07-15015 July 1996 Application for Amend to License DPR-40,revising Description of Reactor Core & Control & Adding Westinghouse Topical Rept List of Analytical Methods,Used to Determine Core Operating Limits ML20112D3151996-05-31031 May 1996 Application for Amend to License DPR-40,adding LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6951996-05-20020 May 1996 Application for Amend to License DPR-40,clarifying Surveillance Test Requirements in TS 3,1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5871996-05-17017 May 1996 Application for Amend to License DPR-40,relocating Operability Requirements for Shock Suppressors (Snubbers) from TS to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20097C3031996-02-0101 February 1996 Application for Amend to License DPR-40,allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool ML20100C0161996-01-22022 January 1996 Application for Amend to License DPR-40 Revising TS Re Requirement for Placing Sirw Tank low-level Channels in Bypass Rather than Trip ML20094N8571995-11-16016 November 1995 Application for Amend to License DPR-40,adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses 1999-09-02
[Table view] |
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BEFORE-THE UNITED STATES g
NUCLEAR REGULAT M COMMISSION In the Matter of Omaha Public Power District ) Docket No. 50-285 2
(Fort Calhoun Station -)
Unit No. 1) .
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APPLICATION FOR AMENDMENT OF OPERATING LICENSE t
Pursuant to' Section 50.90 of the regulations of the U. S. Nuclear i Regulatory Commission ("the Commission"), Omaha Public Power District, holder i of. Facility Operating License No. DPR-40, herewith requests that the Technical Specifications set forth in Appendix A to that License be amended to reflect changes. to .the Limiting Conditions for Operations for the Chemical and Volume Control System. ,
L 'The proposed changes.in Technical Specifications are discussed in Attachment A to this Application. A discussion, Justification and no Significant Hazards Consideration Analysis, which demonstrates that the proposed changes do not involve significant hazards considerations is appended in At+achment 8. The proposed changes in specifications-would not authorize any ounge in the types or any increase in the amounts of effluents or a change in the authorized power level of the facility.
W!!EREFORE, Applicant respectfully requests that the definitions and Sections 2 and 3 of Appendix A to Facility Operating License No. DPR 40 be amended in the form attee.hed hereto as Attachment A.
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g PDR ADOCK 05000285 pg L- -- - - .. _ _ _ , __ . _ _ _ _ .
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'A copy of this Application, including its attachments, has been submitted to the Director - Nebraska State Division of Radiological Health, as required {
by 10 CFR 50.91. l i
, j OMAHA PUBLIC POWER DISTRICT r
By bbion, Manager Nuclear Operations l
-1 1
Subscribed and sworn to beforr ine this lorn day of December,1989.
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notary public f
ENW1407ASY Staa of teasu J.T. CLEASON
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter:of Omaha Public Power District Docket No. 50-285
-(Fort Calhoun Station Unit No. 1) )
AFFIDAVIT K. J. Morris, being duly sworn, hereby deposes and says that he is the Division Manager - Nuclear.0perations of the Omaha Public Power District; that as such he is duly authorized to sign and file with the Nuclear _ Regulatory Commission the attached information concerning the Application for Amendment dated December 20, 1989, concerning the Limiting Condition for 9peration for the Chemical and Volume Control' System; that he is familiar with the content
.thereof;.and that the matters set forth therein are true and correct to the best of his knowledge, information, and belief.
~K.L X M6fris-Division Manager Nuclear Operations-STATE OF NEBRASKA) 1
) ss COUNTY OF DOUGLAS) s-Subscribed and sworn to before me, a Notary Public in and for the State of Nebraska on this Jo M day of December, 1989.
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Notary Public A CINEMI NOTAav. State of Natasta W-T. My la p. July 1990
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ATTACHMENT A "
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,- - 2.0 LIMITING CONDITIONS FOR OPERATION
'2.2 Chemical ' and Volume Control System Applicability Applies to the operational status of the chemical and ' volume' control system.
Objective To define those conditions of the chemical and volume control system ;
necessary to assure safe reactor operation. !
Specifications I (1) ' When fuel is in the reactor, there shall be at least one flow path to the core for boric acid injection.
(2) The reactor shall not be made critical unless all the following minimum requirements are met:
- a. At- least two charging pumps shall be operable, b.- One boric acid transfer pump shall be operable. j
- c. The two concentrated boric acid tanks together shall contain a minimum of 68 inches of a 6-1/h percent to 12 percent by weight boric acid solution at a temperature of at least 200F above saturation te=perature for the concentration present j in the tank.
- d. System piping and valves shall be operable to the extent of establishing two flow paths frem the concentrated boric acid ,
tanks ' to the reactor coolant system and a flow path from the (
SIRW tank to the charging pumps. !
- e. Both channels of heat tracing shall be operable for the above flow paths, f.
Both level instruments on the concentrated boric acid tanks shall be operable.
.(3) Modification of Minimum Requirements 1 i
During power operation, the minimum requirements may be modified !
to allev any one of the following conditions to exist at any one ti=e. If the system is not restored to meet the minimum require- '
ments within the time period specified, the reactor vill be placed in a hot shutdown condition in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. If the minimum requirements are not satisfied within an additional h8 hours, a cold shutdown {
shall be initiated.
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2.0l LIMITING CONDITIONS FOR OPERATION-
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- 2. 2 Chemical and volume Control System (Continued)' -
- a. One of the operable charging pumps may be removed from service provided two charging pumps are operable within -
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i
- b. Both boric acid pumps may be out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. One concentrated boric acid tank may be out of service provided a minimum of 68 inches of 6-1/4 percent to 12 percent by weight boric acid solution at a temperature of at least 20*F above saturation tenperature is contained in the ope - 'e tank ,d provided that t 'e tank is
'es t.. ed 'ble 3tus w' in 24 hr ,
i- s path from the concentrated 'buru acid tanks
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_, ' ear or coolant system may be operable providec rr- e 1er the other flow path from the' concentrated i 50;.. av i ts ";
- the rea ter coolant systen or the i
'RW +'at .o the ci:stging pumps is flu 7: )t .
- rom th, store, to 9-east a sie vitbin 24 nours
- e. O'i channel of ne-c
- acing may De out of service provided
't is restcced to (, s able s>Jtus within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- f. 0ne live. instrument on t.sch concer,trated boric acid tank may be out of service fvr 24 houra. '
Basis The chemical-and coolant system boron volume control (system inventory. l) This isprovides normallycontrol of the reactor accomplished by using any one of the three charging pumps in series with one of the two
. boric acid pumps. An alternate method of boration will be to use the charging pumps directly from the SIRW storage tank. A third method will be to depressurize and use the safety injection pumps. There are two sources of borated water available for injection through three different paths.
~
(1). The boric acid pumps can deliver the concentrated boric acid tank contents (6-1/4 - 12 weight percent concentration of boric acid) to the charging pumps. The< tanks are located above the charging pumps so that the boric acid wfll flow by gravity without being pumped.
(2) The safety injection pumps can take suction from the SIRW tank (at least 1800 ppm boron solution). l Amendment No. Ah, .03 .d GWW w w
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- 2. 0 LIMITING CONDITIONS FOR OPERATION-2.2 2henical and Volume Control System (Continued)
(3)- The charging pumps can take their suctions by gravity from either s the boric acid tanks or the SIRW tank.
- Each concentrated boric acid tank containing 68 inches of 6-1/h weight percent boric acid has sufficient _ boron to bring the plant to a cold shutdown condition. Boric acid pumps are each of sufficient capacity to feed all three charging' pumps at their maximum capacity.
The concentrated boric acid storage tank is sized for a 6-1/h weight' percent -boric acid solution and is capable of storing solution up to 12 veight percent solution. All components of the system are capable of maintaining 12 veight percent solution. The elevation of :the concentrated boric acid tank is sufficiently above the charging pump suction so as to provide- adequate gravity flow to the charging pumps.
Duplicate haating equipment is provided on all components of the '
system to maintain the temperature of the surface to at least 1600F, which is 200F above the saturation temperature of a 12 percent
-solution.~ Malfunction of any heater element vill be annunciated in the control room in sufficient time to energise redundant heater elements before the 200F limit above saturation temperature is reached; the 200F limit also provides assurance that the plant can be shut down before the boric acid precipitation temperature is reached.
The SIRW tank contents are sufficient to borate the reacter coolant in order to reach cold shutdown at any time during core life.
The' limits on component operability and the time periods for in-operability were selected on the basis of the redundancy indicated above and engineering judgment.
References (1) FSAR, Section 9 2 2-19