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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
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Q*[a BEPCRE '!WE UNITED STAM EUCLEAR RBOULA*0RY C0000S310R la the Matter of )
OgWIA PtR' SIC POWER DIS'!EICT ) incket No. 50-265 (Port Calhoun Station, )
. Unit No. 1) )
e s '
M d.. APPLICATIOR TOR AMENDIEDl?
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t ? . OP CPEFATING LTgENSE k,..,Jg
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' pj ;. Pursuant to Section $0.90 of the regulations of the U. 8. Realeer W'.
93 Reguintory Commission ("the Commaission"), Canha Public Power Distriet.
R
@ holder of Pacility Operating' License No. DPR h0, herewith requeste that d.
=
Sections 2.0 and 3.0 of the Tet.hnical Specifications set forth ta Appendia
'.g h,.g"c - A to that Liessee be amended te. specify adaimistrative eestrois used to eq These gi prevent Teactor coolantwsystes, everpressuriaation tr---dents.
e.-
5
,, ( preposed Technical Specifications are submitted in response to a letter.
h dated J oe 28, 1977. receive,4 from O. lear U, 8. Nuclear Regulatory 3
y canaission.
s.,1 x The reoposes changes in Teehateal Specifications are set forth la .
,y Attachment A to this AggMeaties. A discussica, which aanmatrates that , ,
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+
+c 3
the proposed changes da act involve aisafficant baserte cons &dersticas. **
&, to appended in AttatAaeet 3. the proposed changes la spesiftenticas~..'.4...A
~
ui$1:L c
..' he types or angr inerease in the ascents 'g.
g'see16 act subhertse any change in - MC$ c .,
pT of efflusats se ray thange in the authorised power level of the fam
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- iy WHEREFORE, Applicant respectfuuy requests that Sections 2.0 and 3 0 t
of Appendix A to Facility Operating License No. DPR ko be amended la the fers attached hereto as Attmekmont A.
4 E WIAEA PUBuc PodER DISTRICT I
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,/, Division 80maagar -
.* .. Proemeties Operations ammasener.emmeseen Jan0MEL.WD3Nr
. , topte m tae,tes,ad. test i
b,, Subscribed and sworn to before se v a
- this e Y day of /.$ se / , 1977.
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Nq.., O o .. c., / '. 3 /. ,, ,. < ^
Notary Public /
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PORT CALHOUN STATION UNIT NO. 1 LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEN
- y. ) st o _1 - Monitoriter ATAcross Steam Generatort 3 hts pla n t spec 1 tic analysis assumed a 50* h1 between the primary and secondary coolant systens. Please discusses (1) how this br will be nonitored and (2) what coat,tois will be used to 21ait the reactor coolant pump (ac9) starts te er < 50* conditteast Resoonse No.-1
- e .
~*. 'The District has designed a monitoring system which will measure
" the feedwater temperature in each steam generator and compare it wit 2r the reactor coolant system cold leg temperature. This aya-cc' tem will function by draining steam generator feedwater through j
the blowdown system and past temperature elements: one per steam t generator.- Provisions will be made to ensure that the measured h temperature accurately reflects steam generator temperature and N'
annunciation will be provided for AT greater than 500P. Insta11-ation of this' permanent system is scheduled for the 1977 refuel-ing outage.
'l In the event tant material procurement problems prohibit 1977
' installation c.f tne permanent system, thermocouples will be in- _
t stalled on the steam generator shell or secondary-site handholes.
6 Calculations have shown that response time of this system will 4 be sufficiently rapid to allow reasonably accurate determination of steam generator feedwater temperature. This method is oon-4 e sidered to be temporary until receipt of materials allowa in-y, sta11ation of the permanent system.
Operation of reactor coolant pumps relative to the 50er at limitation will be in accordance with the proposed Technical
" specification 2.1.1 and corresponding cperating Instreetions.
C s moquest se. # - 2se2atles Fa2We 42aree d.; j s .; y .
Ja'your analysis yem stated the low temperature overpressere pro ;-
%t tection system wt22 ' met be fully operatieaal natia two oposts g the first eveat is the enabling of the pressste "y PA have occurred.
operated relief valve (PoaFJ 2ew pressere setpotat, the asesed . . ,
.2
~t event is opening the upstream isekatiea seawe. Et is the statt*s p
, ,( positJem that the alara whfeb Jaddeates the need for low tempera- J -
l ture everpressure protectica abou2d met clear matta the 80&F Jew 5;'.'pressere setposat is enabled and the Ase2aties waive la spee. '
[.
(92 ease diseems what steps wA22 be taken to fasure that the Jew ;Y
[temperatore metrefat and the asekation patre positten are wired j
. .together to esaffre that 2ew temperature overpressure proteetdos iv$a availab2e. , 3
- f u.3 I *
. .c ' 2. . N " -b p'.W @ P. W w m v w m g u y , y g , u p s: o y
M@)
~ j:;
- nasoonse No. 2 yi Annunciation wjil be provided on control room pans 1 CB-1/2/3 to indicate closure of either PORV isolation valve. This 7 s A.@
?7 alarm willA not clear until schematic both of this isolation system valvesinhave is shown been the attached opened.
Figure 3.
.a , _ Reevest No. 3 - Sustee insta21ations nn -
D in your analysje you state that the overpressurisation protectica J system will be installed at the nest refue2 LayWeoutage, cetober woeld Jake te
'%r 2977, provided that equipment .mauary is available.
22, 2977 requested yea to
_ $ /g>! reatnd you that our letter of to a schedule for the installation of acceptable Reap tera Q' commit improvement by December 32, 2977.
I hesoonee No. 3 The District is aware of this position, and all possible steps are beint taken to ensure installation by December 31, 1977.
nequest no. 4 - ponv stain sesarakt 24 tu s me plant specific report shows one variab2eIn setpotat suitek order te meet
!. O and one hi-Jow reset switch for both pomre.
the requirements of separabilley of circuits, it is the staff's position that these PonVs should each have a variabJe setpotat
?
l
% mus, the staff betiewee switch and a be there should hi-tow reset switch.
two separate keylocked esteette, one ter coek pens.
- ~ $*\;;
Response No. 4 l
the proposed low setpoint PORY actuation system will be auto-antica11y onebled when cold leg temperature is below 3000F and
$y pressuriser ressure low si 1 (PPL8) has been seed. tbs oommon var le setpoint reset evitches have eliminatet and ocaplete separation of both channels is now maintained.
7 t The attached Figure 1 details the circuitry for PORT PCV-103-1.
A stallar, separate system will be provided for PCV-102-2.
- J g meenent we, s - caresse afaarases
- paesse subale detailed eirente sekeesties and aesto diegreen i
et the everpressure proteettoa system.
\
ananense Mn. 5
):l The attacheA Figures 1 through S detail the preliminary cidealtat scheastics and control layout for the overpressere geotectica~
The following important features are incorporated &ato g;
k gten.e desigan the low setpotat ciroeitry is estcoatically enabled when 1)' 4 preeserteer, pressere 10e signai (9958) is tapessed and h$
3 Response No. 5 (Continued) .
oold leg temperature is below 3600F (contact TCl).
- 2) A key-operated reset switch isOnce necessary to return the the low setpoint is system to the high setpoint.
enabled, it seals in.
- 3) A key-operated switch is provided to allow manual open-While this switch would by-1%g or closing of a PORV.
pass the automatic opening circuitry, it would not by ing pass the low setpoint enabling circuitry. Hanual clos
. of a PORV is annunciated in the control room.
- 4) Enabling or actuation of the' low setpoint circuitry for
.h( one PORV automatically enables or actuates the circuitry
't *for the second PORV.
p 5) Once the low setpoint circuitry has been enabled, an in-crease in RCS pressure above the low setpoint automatically opens the PORY (contact Rl) .
- 6) Annunciatilon is provided if either PORV selector switch
- (switches 2 and 3) is placed in the test position.
Request No. 6 - PoRV Valve cyclines y]*
at what rate does the PoRY cyeZe? Please discuss the eaPabilities Y
et the PORVa under repeated cycling. Can the 50RVs servive opettas
- at the bienest rate for 20 afautesP Response No. 6
^ The low-temperature overpressure protection system is desigasd sash b that, following low setpoint actuation of a p0RV reolosure of i .-
C the 50-100 PORY pai. would not take place until system pressere is re80ste bythis
- PORY eyeling, with the result that eyeling of a 7089 any be treated as a series of individual openings.
7 M' ,-
T. *
- neeueet so. 7 - seismie and rass # Pts Dese itses were met etearly addressed da the plaat speedfie aeport. katify aZZ deviations La the eostros etreetter troe' .
y 8888 319 and seisale erteeria. . ,
paspense no. 7
~ The proposed control circuitry oosplies fully with .1 EBB 279 criteria and is designed as a emissie Class I system.
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f aeeuest me. a - metabi2ieve L
- 7. : ,
@gs please discuss the treguency and type of testing that wA22 be .
- ? meed te determine the eendition et the everpressure proteetion system. It is the statt's positica tha t t (2) the FORF esatro2 etreuitry and pressure detection senser shenad be tested prier to each use of the overprossure protection systcm. and (3) the PORVs shouJd be stroked duriny each refueling.
,f3
% Response No. 8 LW ..
f,% The following surveillance program is proposed for the low set-Nk : q. .
point PORV actuation system:
4 W' 1) The enabling and' actuation circuitry will be tested prior
-t to each scheduled oold leg cooldown below 3000F and monthly 7
,whenever the temperature is below 3000F and the reactor
. vessel head is installed. A test switch mounted in the
-- '4 control room (one per channel) will supply an 'open" sig-
- O nal to the actuation circuitry. Proper operation will be i verified by supervisory and indication lights. See the o attached, Figures 1 and 2 for schematics.
p
,,: 2) .The temperature and pressure channels will be onlibrated
.. each refueling.
2 S 3) The PORVs will be operated each refueling in accordance
- ,7 with the District's in-service inspection program.
.'[r aeeuest no. t- wennice2 eneestiestions s
. m.
O sa pour ama2ysis it was stated that various overpressariaaties M scenaries would be Jiatted by adelaistrative eostre2. It is the
%l esatt*a positten that when adalaistrative eentrole are need to
,Q 22att everpresserisation seenarios, these adotatatrettee eentre2a p should appear la the Behaisa2 speef tications as &inittag Coaditions e for operaties (&cos) . typtea2 &cos whien gom abomad seasider '<..
r'.~ &aeloding La the 9ett Caaneen habeleaa speettieetione are em - .
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