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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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b BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of )
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Omaha Public Power District ) Docket No. 50-285 (Fort Calhoun Station )
Unit No. 1) )
APPLICATION FOR AMENDMENT 0F OPERATING LICENSE I
Pursuant to Section 50.90 of the regulations of the U. S. Nuclear Regulatory Commission ("the Commission"), Omaha Public Power District, holder of Facility Operating License No. DPR-40, herewith requests that the Technical ;
Specifications set forth in Appendix A to that License be amended to delete the -
requirements for the Toxic Gas Monitoring System. l The proposed changes in Technical Specifications are provided in !
Attachment 3 to this Application. A Discussion, Justification and No Significant Hazards Consideration Analysis, which demonstrates that the proposed changes do not involve a significant hazards consideration, is appended in Attachment 1. The proposed changes in specifications would not authorize any change in the types or any increase in the amounts of effluents that will be released, or a change in the authorized power level of the facility. ;
WHEREFORE, Applicant respectfully requests that Specifications 2.22 and 3.1 of Appendix A to Facility Operating License No. DPR-40 be amended in the form attached hereto as Attachment 3.
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.2-l 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.
OMAHA PUBLIC POWER DISTRICT j By #- M l Vice President Subscribed and sworn to before me this 9 day o n a u. , 1995.
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U.S. fluclear Regulatory Commission LIC-94-0258
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i ATTACHMENT 1 l
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M DISCUSSION, JUSTIFICATION AND NO SIGNIFICANT HAZARDS CONSIDERATION DISCUSSION The Omaha Public Power District (0 PPD) proposes to revise the Fort Calhoun Station (FCS) Unit No. 1 Technical Specifications (TS) to delete requirements for the Toxic Gas Monitoring System (TGMS) as contained in TS 2.22 and TS 3.1, Table 3-3, item 29. Currently the TGMS is required to be operational in all operating modes to monitor the fresh air supply to the control room. The TGMS .
samples for six toxic gases and automatically switches the control room HVAC to
- the recirculation mode when gas concentrations reach predetermined setpoints.
This automatic action was designed to provide the control room operators adequate protection from a toxic chemical accident. For additional protection, operators are required to don self contained breathing apparatus (SCBA). ;
The T;MS was installed to meet the control room habitability requirements of NUREG-0737, Item III.D.3.4 " Control Room Habitability," for a postulated toxic chemical release. NUREG-0737 references Regulatory Guide 1.78, which uses r deterministic criteria, as one source of guidance for performing evaluations on toxic hazards. The original submittal approved for FCS (Reference 2 of Attachment 2) followed the guidance of RG 1.78 and identified six potential chemical hazards from on or off-site sources (Chlorine, Hydrochloric Acid, Sulfuric Acid, Hydrofluoric Acid, Hydrazine, and Ammonia). To ensure control '
room habitability following an accidental release of one of these chemicals 0 PPD committed to install a TGMS.
Subsequent to the original submittal, potential on-site sources of chemical releases which required the TGMS for detection have been r(moved (i.e.,
chlorine, hydrogen fluoride) or will be removed in the near future (sulfuric acid). In addition, the remaining on-site and off-site sources have been re-evaluated following Section 2.2.3 cf the Standard Review Plan (SRP), which uses ;
probabilistic criteria for identifying potential hazards. NUREG-0737 references ;
Section 2.2.3 of the SRP as another acceptable method for identifying design !
basis toxic hazards. Following this guidance, it has been concluded that the TGMS is not necessary as it only improves control room habitability for certain very low probability events.
Since its installation, the TGMS has been a maintenance burden. 'The maintenance i difficulties arise from the fact that the system requires the use of very ;
sensitive instruments and very low actuation setpoints. OPPD has spent and ;
continues to spend significant resources on calibration, preventative '
maintenance, and corrective maintenance activities to ensure continued operation of the TGMS. This effort has been increased recently due to the original I equipment manufacturer discontinuing its 10 CFR 50 Appendix B program which will require OPPD to either replace the TGMS or commercially dedicate replacement components.
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The benefit of improved control room habitability is outweighed by the associated maintenance costs and the distractions the system imposes on the control room operators in ensuring that the TGMS remains operable. Thus, it is proposed that TS 2.22 and 3.1, . Table 3-3, item 29, be deleted. It is OPPD's intention that if the proposed changes are approved, the TGMS would be completely deactivated. The removal of the TGMS will eliminate the automatic initiation of the control room HVAC recirculation mode. However, the ability to i manually place the HVAC system into the recirculation mode will be retained.
JUSTIFICATION To justify removal of the TGMS, the deterministic criteria of RG 1.78 were used as screening criteria. For events which exceeded these screening criteria, the probabilistic criteria of SRP Section 2.2.3 were applied. Application of these >
regulatory criteria is consistent with the guidance provided by NUREG-0737, and with the Safety Evaluation Report for Vermont Yankee's Technical Specification Amendment No. 132 (Docket 50-271, supporting Amendment to Facility Operating >
License No. DPR-28, dated October 24,1991). .
Attachment 2, " Analysis to Support Removal of the Fort Calhoun Toxic Gas Monitoring System," documents the analysis with respect to these regulatory ,
criteria. The analysis was updated from that approved by Reference 2 of l Attachment 2, with regard to potential chemical hazards in the vicinity of FCS, I the chemicals considered potentially toxic, and the corresponding toxicity limits. The off-site sources evaluated included those that are, or are expected to be, used at nearby locations in appreciable quantities. The results show that all chemicals satisfy the RG 1.78 screening criteria, with the exception of I ammonia, carbon dioxide, sulfur dioxide, and chlorine. For the chemicals not I meeting the criteria of RG 1.78, the probability of a 10 CFR 100 fission product releas'e is acceptable since the frequency of an event leading to the lack of control room habitability is well below the threshold for consideration as a design basis event in accordance with SRP Section 2.2.3. Thus, the TGMS is not required to satisfy the provisions of NUREG-0737, Item III.D.3.4.
The analysis presented in Attachment 2 includes both deterministic and probabilistic analyses. The deterministic analyses follow the general guidance of RG 1.78 and include the following:
- 1. A list of hazardous chemicals
- 2. A toxicity limit for each chemical
- 3. Consideration of chemicals shipped or stored within five miles of FCS
- 4. Consideration of chemicals shipped more frequently than 10 times per year by truck and 30 times per year by rail
- 5. Methodology for calculating dispersion of a puff release. !
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The deterministic analysis follows RG 1.78 methodology with the exception of the list of chemicals and the toxicity limits. A more comprehensive list of chemicals, the EPA's list of Extremely Hazardous Substances, was used in the analysis along with the RG 1.78 list in order to identify potentially toxic chemicals. The toxicity limits (except for Carbon Dioxide) were based on the National Institute of Occupational Safety and Health (NIOSH) concentrations for "Immediately Dangerous to Life and Health" (IDLH) which is referenced by the EPA list for acute toxicity limits. Although the limited list of chemicals in RG 1.78 does not provide toxicity limits for all chemicals considered in the analysis, the IDLH values are considered to be consistent with the RG 1.78 time frame for a two minute exposure. Thus, OPPD considers the deterministic analysis presented in the attached report to be a comprehensive analysis which I is consistent with the general guidance and intent of RG 1.78. The analysis results show that all chemicals except for ammonia, sulphur dioxide, carbon dioxide, and chlorine meet the deterministic screening criteria of either:
- 1. control room concentrations never reach toxic limits, or
- 2. there is at least two minutes between the time that the toxic gas is detectable by smell by the operating crew and the time the toxic limit is reached.
For chemicals that did not meet the above screening criteria, the analysis presents the results and methods for a probabilistic analysis to determine the frequency of a conditional core damage event resulting from an off-site chemical release (on-site chemicals were screened out by deterministic analysis). The I analysis accounts for the transportation, pipeline, and off-site storage accident frequency; the effects of meteorology on plume dispersion; and on the plant response. The results show that the estimated frequency of such an event leading to core damage is orders of magnitude less than the SRP Section 2.2.3 guideline of IE-7 to IE-6 per year. Thus, toxic gas events are well below the threshold for consideration as a design basis event.
The results of this analysis, as summarized in Attachment 2, demonstrate that the NUREG-0737 requirements for control room habitability following an on-site or off-site toxic chemical release are met without the need for a TGMS.
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BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION:
The proposed changes do not involve a significant hazards consideration because operation of Fort Calhoun Station Unit No. 1 in accordance with these changes would not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated.
The previously evaluated accidents affected by this change are the on-site and off-site toxic chemical releases. These events have been re-evaluated for this proposed change and have been shown to meet the applicable regulatory screening criteria. The deterministic analyses performed show that the guidelines of Regulatory Guide 1.78 for control room habitability are met for on-site and most off-site chemicals. On-site chemical sources originally present when the toxic gas monitoring system was installed have been removed from site or determined not to exceed the deterministic analysis screening requirements. For those off-site chemical releases which did not meet the deterministic screening criteria a probabilistic analysis was perfsrmed. The probabilistic analysis performed in support of this proposed change shows that the probability of an off-site chemical release leading to 10 CFR 100 consequences is orders of magnitude less than the SRP 2.2.3 guidelines. These results show that there is no significant increase in the probability or consequences of any accident previously evaluated.
(2) Create the possibility of a new or different kind of accident from any previously analyzed.
Only events involving chemicals for which the TGMS provides an automatic detection / isolation function are affected by this change. As stated above, the potential events involving these chemicals have been re-evaluated using the appropriate regulatory guidance and shown to satisfy either the deterministic screening criteria of RG 1.78, or to be probabilistically insignificant compared to the guidelines of SRP Section 2.2.3. These results show that the proposed change will not create the possibility of a new or different kind of accident from any previously evaluated. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously analyzed.
(3) Involve a significant reduction in a margin of safety.
The margin of safety is defined by the regulatory basis for the existing TGMS, namely NUREG-0737, Item III.D.3.4. The analysis provided to support this proposed change follows the regulatory guidelines of RG 1.78 and SRP Section 2.2.3, as specified in NUREG-0737, Item III.D.3.4. The analysis shows that the applicable regulatory criteria are met and the proposed changes do not involve a significant reduction in a margin of safety.
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Therefore based on the above, it is OPPD's position that this proposed amendment does not involve a significant hazards consideration as defined by 10 CFR 50.92 and the proposed changes will not result in a condition which significantly i alters the impact of the Station on the environment. Thus, the proposed changes ,
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meet the eligibility criteria for categorical exclusion set forth in 10 CFR '
t 51.22(c)(9) and pursuant to 10 CFR 51.22(b) no environmental assessment need be prepared.
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