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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
[Table view] |
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---* *- - -- --------- ---~-- --- -*- ----- --- - -- --- -coNsTJMERs--POWER___COMPANY -
Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below:
I. Changes Revised Technical Specifications pages are attached. Proposed changes are shown by a vertical line in the right-hand margin. The following sections of the Technical Specifications are affected by these proposed changes: Section 3.3, Section 3.5.1 a - f, Section 3.5.2 a - e, Section 3.5.3, Section 3.5.4, Section 3.5, Section 3.17 - Table 3.17.4, Section 4.6.1.c, Section 4.9 and Section 4.1 - Table 4.1.3. The following is a brief description of each change:
Specification 3.3 "Basis" - Change last sentence to reflect two rather than three high-pressure safety injection pumps.
Specification 3.5.1.a - The existing Specification refers to the operability of both pumps implying the existence of only two pumps. As a result of the Auxiliary Feedwater System Modifications, the Plant will have three auxiliary feedwater pumps thus this specification now refers to the operability of all three pumps. Operability of the steam driven pump has been changed to reflect the fact that full flow conditions can not be established at 325°F.
Specification 3.5.1.-b*- This is a new Specification which makes Plant personnel aware of.Auxiliary Feedwater System instrumentation operability requirements which are not addressed in Specification 3.5 Specification 3.5.1.c ~This is a new Specification which specifically defines the operability requirements of the Auxiliary Feedwater System flow control valves prior to heating the Plant.
Specification 3.5.1.d - Same as existing Specification c except "are" is changed to "shall be".
Specification 3_. 5 .1. e - Same_ as existing Specification b _except fire pump operability statement has been deleted since it is redundant with 3.5.1.a.
Specification 3. 5 .1. f - Same as existing Specification d. except "are" is changed to "shall be".
8511010059: B~A~~55 '. -! :;_.
~DR . ADOCK 0 . PPR LJ
I Specification 3.5.2 - Same as existing Specification 3.5.2 except the action statement has been changed to refer to new Specification 3.5.3.
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condition of operation when auxiliary feedwater pump P-8A or P-8B is inoperable. A period of 7 days is given to restore the affected pump to operability. A period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is given to restore P-8C to operability.
Specification 3.5.2.b - This is a new Specification. Permitting testing of the third AFW pump necessitates placing the controls of up to two other pumps in manual.
Specification 3.5.2.c - This Specification is a revision to existing Specification 3.5.2.b. A period of 7 days was given to restore the alternate fire water suction.
Specification 3.5.2.d - This is a new Specification giving a limiting condition of operation when alternate suction from the Service Water System to pump P-8C is not available. A period of 7 days was given to restore the alternate service water suction.
Specification 3.5.2.e - This is a new Specification giving a limiting condition of operation when one or two of the Auxiliary Feedwater System flow control valves is inoperable. A period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is given to restore the flow control valves to operability.
Specification 3.5.3 - This is a new Specification which gives specific direction on what action to take if the requirements of 3.5.1 or the conditions of 3.5.2 cannot be met.
Specification 3.5.4 - This Specification is almost identical to existing Specification 3.5.4, but it refers to all auxiliary feedwater pumps instead of both auxiliary feedwater pumps.
Specification 3.5 Basis-- -This Section was revised to-give a more accurate description of the Auxiliary Feedwater System. Included in this basis document is a brief description of the pump start sequence.
Specification 3.17, Table 3.17.4, Item 13 - This is a r_evision to an existing Specification. This Specification concerns the requirements for remote auxiliary feedwater flow indication available to operators.
It includes a new footnote (h) that specifies an action statement consistent with a given control valve.
Specification 3.17, Table 3.17.4, Item 14 - This Specification concerns the 9p~r~bility of_ the Au~i_liary _Feedwater Actuation _system Sens9r Channels which receive steam generator level signals and make a determination if they exceed specified setpoints.
Specification 3.17, Table 3.17.4, Item 15 - This Specification concerns the operability of the Auxiliary Feedwater Actuation System Actuation Channels which receive trip signals from the sensor channels and then generate the appropriate signal to the Auxiliary Feedwater System equipment.
TSOP1085-0308-NL04
3 Specification 3.17, Table 3.17.4, Item 16 - This is an existing Technical Specification numbered as Item 15 on Table 3.17.4.
Specification 4.1, Table 4.1.3, Item 15.a -- The monthly AFw-pump -check by comparison of channels of the flow indication is deleted. Existing item 15.b is change to item 15.a Specification 4.1, Table 4.1.3, Item 16a - The channel description is changed from "Auto Initiation" to "Start" and the surveillance method is changed from "internal test signal" to "switch" to more*accurately reflect the actual surveillance test performed.
Specification 4.1, Table 4.1.3, NOTE 3 has been revised to state that the auxiliary feedwater pumps will be started from the control room hand switch, from the breaker (or alternate steam supply), and from the pump test - key switch in a three month period; this is a more accurate description of what is performed in the Surveillance Test.
Specification 4.6.1.c - This specification revision deletes reference to HPSI pump P66C which is now referred to as auxiliary feedwater pump P-8C.
Specification 4.9 - Specification a, b, and the Basis have been revised
.to reflect the surveillance requirements of the Standard Technical Specifications consistent with format and concept within the constraints of the existing plant design and construction.
II. Discussion The above proposed Technical Specifications changes are requested.
Specification 3.3, "Basis" and Specification 4.6.1.c - In response to NUREG-0737 Action Item II. E.1.1, "Auxiliary Feedwater System Evaluation, Consumers Power Company proposed, in a letter dated November 2, 1981, to modify the existing Palisades Piant design. -Proposed Technical Specifications were submitted by letter dated August 29, 1983. The design modification adapted the existing spare high pressure safety injection (HPSI) pump, P-66C, for auxiliary feedwater service. This design modification has been accepted by the NRC (reference Amendment No 83 dated June 19, 1984), and Consumers Power Company completed this modification during the 1983-1984 refueling outage. The above proposed Technical Specifications change is requested to bring the Palisades Technical Specifications into conformance with the actual as-built plant design.
Specification 3~5.1.a See Section I.
Specification 3.5.1.b - See Section I.
Specification 3.5.1.c - If the Plant is in cold shutdown and one of the flow control valves is malfunctioning, the valve should be repaired prior to heating the Plant to ensure total Auxiliary Feedwater System operability.
Specification 3.5.1.d,e,f - See Section I.
TSOP1085-0308-NL04
Specification 3.5.2.a - If P-8A or P-8B is inoperable, the Plant still has two independent and redundant auxiliary feedwater pumps complete 4
with associated equipment to Supply <_l,UX_i_liary feedwater to the -steam generators. However, i f P-8A or P-8B is in~perable.. the- reduncfancy or--
the auxiliary feedwater system is reduced. Therefore, although inoperability of P-8A or P-8B is not a serious deficiency it is not advantageous for the Plant to have one of these pumps out of service as a normal Plant condition. If P-8C is inoperable, the Plant still has one Auxiliary Feedwater System pipe train available to supply auxiliary feedwater to the steam generators. The limiting condition of ' operation of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for pump P-8C is consistent with the Standard Technical Specifications.
Specification 3.5.2.b - See Section I Specification 3.5.2.c - The auxiliary feedwater system now has 2 secondary suction sources to the auxiliary feedwater pumps. The current Technical Specification 3.5.2.b has a limiting condition of operation time period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the alternate fire water suction to the auxiliary feedwater pumps P-8A and P-8B. With an additional independent secondary suction source to auxiliary feedwater pump P-8C, the time limit on the subject limiting condition of operation need not be as stringent. Therefore, the time limit on the subject limiting condition of operation is extended to 7 days.
Specification 3.5.2.d - A period of 7 days was selected to be consistent with Specification 3.5.2.c. The auxiliary feedwater system now has 2 secondary suction sources to the auxiliary feedwater pumps. The current Technical Specification 3.5.2.b has a limiting condition of operation time period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the alternate fire water suction to the auxiliary feedwater pumps P-8A and P-8B. With an additional independent secondary suction source to auxiliary feedwater pump P-8C, the time limit on the subject limiting condition of operation need not be as stringent. Therefore, the time limit on the subject limiting condition of operation is extended to 7 days.
Specification 3.5.2.e - One or two flow control valves may be inoperable, provided the Plant still has one Auxiliary Feedwater System pipe train available to supply auxiliary feedwater to the steam generators. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limiting condition -of operation is consist.ent with that of pump P-8C.
Specification 3.5.3 - See Section I.
Specification 3.5.4 - See Section I.
Specification 3.5.- Basis - See Section I.
Specification 3.17, Table 3.17.4, Item 13 - In the Auxiliary Feedwater System, there are 2 remote flow indicators per flow control valve. It is necessary to have at least 1 remote flow indicator operable on each flow control valve for an operator to know how much water the auxiliary feedwater system is pumping to the steam generators and what steps he should take to adequately control auxiliary feedwater flow. New footnote (h) specifies an action statement consistent with a given flow control valve.
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5 Specification 3.17, Table 3.17.4, Item 14, - There are four Auxiliary Feedwater Actuation System Sensor Channels. Two of the four sensor channels _must_ t:rip f9r the _Auxiliary Feedwater Actuation System actuation channels to trip. I f 1- se-nsor- channel :ls inoperabie, the logic then is 2 out of 3 sensor channels must trip for the actuation channels to trip. If 2 sensor channels are inoperable, the logic is then 2 out of 2 sensor channels must trip for the actuation channels to trip. NOTE F states one of the Inoperable low level bistable modules (one for each steam generator) of an inoperable sensor channel must be in the tripped condition if two sensor channels are inoperable. Thus, if two sensor channels are inoperable, the logic for the automatic pump start signal would be 1 out of 2. These conditions are very similar to what currently exists.
Specification 3.17, Table 3.17.4, Item 16 - See Section I.
Specification 4.9, - See Section I.
Specification 4.1, Table 4.1.3, Item 15 and 16 - See Section I.
Specification 4.1, Table 4.1.3, NOTE 3 - See Section I.
Analysis of No Significant Hazards Consideration This change request results from a modification that utilized a spare high-pressure safety injection pump to provide a third auxiliary feedwater pump with its own independent auxiliary feedwater train to both steam generators. In addition to the new auxiliary feedwater train, the system now has 2 secondary suction sources to the auxiliary feedwater pumps. The modification responded to Item II.E.1.1 of NUREG-0737, Long Term Auxiliary Feedwater System Evaluation. The modification improves the reliability and performance of the auxiliary feedwater system.
The requested specification changes reflect operability, action statements, surveillance requirements and basis for the new system.
They are consistent with the format and content requirements of the Standard Technical Specifications within the constraints of the existing plant design and construction. The limiting conditions of operation (LCO) for the auxiliary feedwater pumps P-8A and P-8B however have been extended from 3 days to 7 days. The change request also reduces the existing flow testing of the system from monthly to quarterly in accordance with the ASME B&PV Code requirements. The LCO extension and the reduction in flow testing from existing Technical Specification requirements are consistent with the improved reliability and performance of the auxiliary f eedwater system. Therefore this request does not involve an increase in the probability or consequences of previously evaluated accidents since system reliability has been improved. Based on engineering judgment and the partially completed Probabilistic Risk Assessment for Palisades Plant, it is concluded that quarterly flow testing of the AFW system is optimum in establishing operability yet providing for a reduction in the th~rmal cycling of the AFW inlet nozzles on the steam generators. Furthermore, the design of the new nozzles incorporates the results of our analysis of the previous failed sparger thermal liner and external piping to assure a different or new type accident is not created. Therefore, this proposed change TSOP1085-0308-NL04
request does not create the possibility of a new or different kind of accident from any accident previously evaluated.
6 The *changes proposed by- the re*quest invoJ:ve afi increase in the -1tlafgiri of safety as defined in the proposed Technical Specification Basis. The Auxiliary Feedwater System is designed so that an automatic start signal is generated to the auxiliary feedwater pumps upon low secondary side steam generator level. If pump P-8A fails to start or establish flow within a specified.period of time, pump P-8C receives an automatic start signal. If both pumps P-8A and P-8C fail to start or establish flow within each pump's specified period of time, auxiliary feedwater pump P-8B receives an automatic start signal. The previous margin of safety was established via the operation of only two pumps. The service water makeup to the auxiliary feedwater pump suction in addition to the firewater suction source also contributes to an increase in the margin of safety.
Therefore, the change does not involve a significant hazards
III. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no significant hazards consideration. This change has also been reviewed under the cognizance of the Nuclear Safety Board. A copy of this Technical Specification Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.
CONSUMERS POWER COMPANY By, fif)/!JdJ/!JC R B DeWitt, Vice President Nuclear Operations Sw6rn and subscribed to before me this 28th day of October 1985.
1987.
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