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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] |
Text
. .
L .'
BEFORE THE UNITED STATES NUCLEAR REGULATORY C0KMISS10N in the Matter of )
)
Omaha Public Power District ) Docket No. 50-285 (Fort Calhoun Station )
Unit No. 1) )
APPLICATION FOR AMENDMENT OF .
OPERATING LICENSE 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 Section 2.1.6 of the Technical Specifications set forth in Anpendix A to that License be amended to change the Limiting Conditions for Operation of the Main Steam Safety Valves.
The proposed changes in Technical Specifications are discussed in the Application for Amendment dated June 28, 1991. This application only provides numerical values for the safety valve setpoints and therefore does not affect the discussion, justification and no significant hazards consideration transmitted in the Application for Amendment dated June 28, 1991. The proposed changes in specifications would not authorize any change in the types or any increase in the amounts of effluents or a change in the authorized power level of the facility.
WHEREFORE, Applicant respectfully requests that Sectinn 2.1.6 of Appendix A to facility Operating License No. DPR-40 be amended in the form attached hereto as Attachment 3.
[?[kNh db P
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t-A copy of this Application, including its attachments, has been sub-mitted to the Director - Nebraska State Division of Radiological Health, as required by 10 CFR 50,91.
OMAHA PUBLIC POWER DISTRICT By t$'--
Acting Division Manager Nuclear Operations Subscribed and sworn to before me this M day of November, 1991.
p ga m ie m -siend*****I
, MELYA L EVANS c,s )
y-(. . G%) LT' t
Notary Public
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMHioS10N in the Matter of )
)
Omaha Public Power District ) Docket No. 50-285 (Fort Calhoun Station )
Unit No. 1) )
AFFIDAVIT T. L. Patterson, being duly sworn, hereby deposes and says that he is the Acting Division Manager - PJclear Operations of the Omaha Public Power District; that as such he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached itiformation concerning the. Application for Amendment dated 11/27/91, concerning revision of Main Steam Safety Valve Setpoints'; 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.
s -
Y k_[q [N_
Acting Division Manager Nuclear Operations STATE OF NEBRASKA)
, ) ss COUNTY OF DOUGLAS) l Subscribed and sworn to before me, a Notary Public in and for the State of Nebraska on this 21 day of November, 1991 '
A ggggut sqtART* $tste el ht46&M Q
3 T
$ MELVA L EVANS b 0DL O',.
1 ATCLso &k us toa t** D ' N Notary Public s 4 - -. n -
4
ATTACHMENT 1 OVEST10NS ON FORT CALHOUN MSSV AMENDMENT RE0 VEST Question No, i: Technical Specifications 2.1.6(3) requires only that eight of the 10 main steam safety valves (MSSVs) be operable with their lift settings maintained between 1000 psia and 1050 psia +3/-2% of the nominal nameplate setpoint values, lhe MSSV open setpoint assumed in the loss of Feedwater Flow analysis is 1066 psia, which could be nonconservative compared to the actual settings since safety valves are allowed to operate at higher settings values than the analysis values. Provide the li'. settings for all the MSSVs on Technical Specification 2.1.6.
Answer No. 1: Attachment 3 contains replacement pages for OPPD's
" Application for Amendment of Operating License" submitted by Reference 2, which seeks to amend Section 2.1.6 of the Technical Specificatic~.s. The changes requested pertain to limiting Conditions for Operation of the Main Steam Safety Valves.
The replacement pages only provide numerical values for the safety valve setpoints and therefore do not affect the discussion, justification and no significant hazards considerations contained in Reference 2.
- Question No. 2: See Attachment 2 for reply.
Question No. 3: See Attachment 2 for reply.
l
ATTACHMENT 2 Question 2: Explain and justify in de' ail how steam generator and pressurizer safety valves were modelled in the analyses for overpressurization events, especially the model-ling assumptions for the valve accumulation, blowdown, and setpoint tolerance. Identify the locations of the max l mum RCS and secondary pressures for overpressurization events, Response 2: The main steam safety valve blowdown and accumulation model contained in the CESEC code is shown in the attached Figure A. The pressurizer (primary) safety valve blowdown and accumulation model is shown in Figure B.
f The setpoint tolerances were varied and a number of computer runs ovete made to deter-mine thu system response sensitivities with various corribinations of setpoints for the Main Steam Satety Valves (MSSVs) and the Primary Safety Valves (PSVs) for the limiting tran-sients. For Fort Calhoun the limiting design basis transients have been determined to be the Loss of Load event for the primary system and the Loss o' Feedwater event for the sec-ondary system. These limiting transients were established by OPPD and Combustion En-gineering during the benchmarking of the CESEC code and the reload analyses per-
, formed for the 2700 MWt analog plants and Fort Calhoun. The transient resuits indicated that a setpoint drift of up to + 5% for both the MSSVs and the PSVs would satisfy the accep-tance requirements 'or the events. For conservatism, however, a value of +3% was se-lected for incorporation into the facility license change request. Only 8 of 10 main steam safety valves were assumed to be operable, in accordance with the Technical Specification requirements (1015,1025,1040 and 1050 psia)
The maximum pressure location for the primary system for the Loss of Load and Loss of Feedwater events is in the Reactor Coolant System while the secondary peak pressure is -
located at the Steam Generator. CESEC does not have the modelling fidelity to provide more concise locations. If the NRC approves the CENTS code for use by OPPD then a more accurate location can be identified due to the larger number of nodo locations calcu-lated.
Question 3: Discuss the peak RCS and secondary pressures for the relevant overpressur-ization transients such as Turbine Trip, Feedlir e Break, and Locked Rotor analyses with the increased setpoint tolerance.
Response 3: The Turbine Trip without simultaneous reactor trip is called the Loss of Load (LOL) analysis in the Fort Calhoun USAR. The LOL used a conservative, bounding analysis to calculate the peak pressures. Enclosed is Table 1 for the input parameters, sequence of events summary (Table 2) and Figures 1-1 through 1-4 indicating the system re-sponses from the +3% drift case. The +3% drift case was one of thc cases that were run ,
as part of the sensitivity analysis. The safety valve opening point in iicated in the summary (Table 2) is for the first valve accounting for setpoint drift and accumulation.
I
_ . _ _ _ . __ _ _ _____._ _ _ _ _ _.~ _._.___.__.. _ _ __. . _ _ _ _.
4 The Feedwater Une Break Accident, analyzed as an overpressure / partialloss of RCS heat removal capacity event, is not part of the Fort Calhoun design basis and was not specifical-ly considered as such in the initiallicense application. In Appendix M of the Fort Calhoun i
Station USAR the feedwater line break is examined and shown to be bounded by the steamline break, as a RCS overcooling / excess heat removal event, in response to an NRC question during closure of NUREG-0737, item II. " 2, OPPD responded to the specific NRC question at the time rather than identifying Uh. R Appendix M as the reason for not providing a steam space volume. It is OPPD's posi, un that in providing this information no commitment was made to revise the Fort Calhoun Station design basis by including the feedwater line break (as an overpressurization event) as a USAR Chapter 14 postulated accident.
- The Locked Rotor event is described as the Seized Rotor event for Fort Calhoun. The Seized Rotor event was not specifically analyzed for the increased setpoint drift since the transient does not have sufficient time to develop due to the reactor trip on low flow within the first few seconds of the initiation of the event. This willlimit the temperature and pres- -
sure increases for the event to a level much less than the limiting event, ,
i 2
_ . . _ . _ . _ _ _ . _ . . ~ . . _ - . _ _ _ . . _ __...__ _ _ _ __ ._. -
l
?
FIGURE A -
SECONDARY SAFETY VALVE CHARACTERISTICS .
FRACTIONAL VALVE FLOW AREA FRACTIONAL VALVE FLOW AREA
- WHEN INLET PRESSURE REACHES WHEN INLET PRESSUREDOES NOT -
GREATER THAN OR EQUAL TO 3% REACH 3% ABOVE THE VALVE SET
- ABOVE THE SET PRESSURE DURING PRESSURE DURING ATRANSIENT-A TRANSIENT. .
- 1.0 1.0 ;
O_t E / ,',- 0 3
$ 6 j/,/
$.0.7 $ 0.7 _ __
- [- p 1
-z z I O- I o I i:: - I c: I b
-O I i
< 1 < l
@- l @ l l
- - l 0.0 0.0 I 1 SET SET
-21/2%-PRESSURE 3%
-21/2% 3%-
PRESSURE
-VALVE INLET PRESSURE VALVE INLET PRESSURE OPENING CLOSING 3
w w k '
i-s=d' -*m - T- 'T+mm--M
4 4 FIGURE B PRIMARY SAFETY VALVE CHARACTERISTICS 1.0 -
f-UI E
'/
5
$ 0.7 -
_ I
< l z 1 9 I
& l u
- < I m l l 1 1
! l I '
0.0
-5% -1% SET l PRESSURE 1
VALVE INLET PRESSURE I OPENING l
I ------
CLOSING L
4
1 Table 1 FORT CALHOUN CYCLE 11 KEY PARAMETERS AS$UMED IN THE LOSS O!
LOAD TO BOTH STEAM CENERATORS ANALYSIS farmetrt un,tig
' value initial Ce,re Power Level MWt 1530 (102n)
Initial Core Inlet Temperature 'T 547 Initial Pressurizer Pressure psia 2,053 Initial Steam Generator Pressure psia 815 tuittal hCS Flow' Rate gpm 196.,000 Moderator Temperature Coefficient 10"' ap/'F + 0.5 Fuel Temperature Coefficient 10 ap/*F Least negative-
. predicted during core life.
Fuel Temperature Coefficient Multiplier 0.85 CEA Time to 1004 Insertion (Including Holding coil Delay) sec. 3.1 Scram Reactivity Worth gap
-6.65 Kinetics Parameters A
.004696 Allowable Primary and Secondary Safety Valve Setpoint Drift' %
+3 i'
l l
9
- - , < , e -,
Table' 2-FORT CALHOUN CYCLE 11 SEQUENCE OF EVENTS FOR THE LOSS OF: LOAD EVENT-I_0 MAXIMlZE CALCULATED RCS PEAX PRESSURE '
1 Time (sec)_
Event E Setooint or value 0.0 Loss of Secondary Load ----
i 6.8 Steam Generator Safety Valves Open 1066 psia 8.9 High Pressurizer Pressure Analysis 2422 psia Trip Setpoint is Reached-10.2 CEAs Begin to Drop Into Core ,
10.6 Pressurizer Safety Valves Open 2575 psia 11.3.
Maximum RCS Pressure 2649 psia -
-14.4 - -
Maximun. Steam Generator Pressure 1078 psia-4 I
mm-+ ,-n-- .<- , , , , - 4 vn.-, , - - - , , - --v, m m-m-- -~w e n kw w v W,n- - = - -- r =-e-amv e
l!
t 120; ,
1 I <
3 -
i 110 - .
l 1 '
- j 100 - !
90 -
x ._
O 80 -
O i i m i 70 - i '
a j -
t a* 60 -
.c= -
W- 50 --
a a ._
so- 40 -
a _
30 -
20 -
10 -
0- '
E._ i
~
0- 15 30 45 60 75 l
TIME, SECONOS I
055 Of l.080 Pyent' t r0re p0'eer vs. ,;..123 i 9 mBDa UbllC P0' der District Figure '
F0rtCalh000 Station-UnitNO.! 1-1
5 2700 4
, i i
2600-L .
l J.
i i
2500 -
1 i
2400- -
I l
>-a i
$ 2300 -
f s l
w M c-3 2200
.m m -
ct Q. !
m 2100: -
r3
, . x. -
2000 -
1 1 _
s 1900 -
1800 -
~ _
4 1700 -
0- 15 30 45- 60 75 TIME, SECONDS 4
LossofLoadE 1CS Pressure Ilmevs. vent 0.manaPublicPowerDistrict i Figure FortCalhounStation-Unit 110.i t-z y y -
g
4 -
-g 620.
i-i 1 610 -
}n "
\
\
/
600 u.
LO 590 -- T ay, '
1
.J vi w
x '\ '\
3 580 \
//
,c< N M 570 -
m T f x'\NN e
560 -
NNNNb N N';x -
550 -
~%N 540 ' ' ' '
0 15 30 45 60 75-TIME, SECONDS I
LossofLoaaEvent I RCS Temaeratures vs. Time- Omana Public Power District Figur'el Fort Calhoun Station-Unit flo. I t -
4- - - _ . . _ .
,- l l
1100 -
i . , .
[ i f
/ \ i 1050 -
1 \
1
( -
l Q- ,f '
< - 1000
& 1 I -
j
- a. '
ui.
c= i 5-m 950 - -lt
.E~
l e: .
m 900 J 850 800 ' ' ' '
0 15 30 45 60 75
-TIME, SECONDS E
i LOSS-otLaaaEvent SteaaGeneratorPressurevs. Time OmanaPublicPowerDistrict Fiqure '
Fort Calhoun Station-Unit No. I 1-4
._ ..- __