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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
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consumers Power David W. Rogers Plant Safety and Licensing Director POWERiNii MICHlliAN'S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 October 5, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - TECHNICAL SPECIFICATIONS CHANGE REQUEST - PRIMARY COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITS.
A request for a change to the Palisades Technical Specifications (TS) is enclosed. This Technical Specification change request (TSCR) addresses three related items:
- 1) It proposes revised Primary Coolant System (PCS) Pressure-Temperature (P-T) limits, PORV setting limits, and Primary Coolant Pump starting limits to accommodate reactor vessel fluence for an additional four effective full power years (up to 2.192 x 10 19 nvt). The existing P-T limit curves are calculated for a fluence of 1.8 x 10 19 nvt, which could be reached as early as March 1, 1995.
- 2) It proposes requiring the High Pressure Safety Injection (HPSI) pumps to be "rendered incapable of injection into the PCS" when the PCS is below 300°F, rather than the existing requirement to render both HPSI pumps "inoperable" when the PCS is below 260°F. This change supports the assumption in the P-T limit analyses that HPSI injection would not* occur below 300°F.
- 3) It proposes a more restrictive limit on pressurizer heatup rate to achieve consistency between design assumptions and TS limits. The limit in the existing TS is less restrictive than used in design calculations. Neither the design heatup rate nor the TS heatup rate limit is achievable with installed equipment.
The attached change request provides a description and discussion of the proposed changes. The following attachments have been included:
- 1) Proposed TS pages.
- 2) Existing TS pages, marked to show the changes.
- 3) Engineering Analysis EA-A-PAL-92095?01, Rev O; "Pressure Temperature Curves and 19LTOP Limit Curve for Maximum Reactor Vessel Fluence of 2.192 x 10 Neutron/cm 2 "
,- - -- ~ - -- - - -- ---- ----
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r The existing PCS P-T limits were calculated for a reactor vessel wall fluence of 1.8 x l0 19 nvt. That fluence may be reached as soon as March 1, 1995. It is requested, therefore, that the TS Amendment be approved by January 3, 1995 with 60 days after approval for full implementation, to allow for the necessary training and procedure revision.
This Technical Specification change request contains two pages (i and 4-6) which contain changes proposed in our Instrumentation and Control Technical Specification change request. That change request is currently in the final stages of the NRC review and approval process.
Summary of Commitments:
This letter completes a commitment made in our August 26, 1992 letter entitled "HEATUP AND COOLDOWN PRESSURE/TEMPERATURE LIMITS - TECHNICAL SPECIFICATIONS" to submit a request to change these limits.
David W. Rogers Director, Plant Safety &Licensing CC Administrator, Region III, USNRC Resident Inspector, Palisades Attachments I
I
CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 It is requested that the Technical Specifications (TS} contained in the Facility Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on February 21, 1991, for the Palisades Plant be changed as described below:
I. Discussion of Proposed Changes This Technical Specification change request addresses two separate, but related, issues; revised Primary Coolant System (PCS} P-T limits which accommodate additional accumulated reactor vessel fluence and revised High Pressure Safety Injection (HPSI} pump limits for shutdown operation to support assumptions of the analyses for the revised P-T curves.
A. Revised PCS P-T Limits:
Three specifications are affected by the proposed P-T limits:
Specification 3.1.lh, Primary Coolant Pump (PCP} starting limits_;
3.1.2, PCS P-T and Heatup-Cooldown limits; and 3.1.8, Low Temperature Overpressure Protection.
PCP Starting Limits, 3.1.lh:
PCP starting limits were revised to provide more generalized starting conditions for the first pump. These limits are intended to assure protection of both the PCS and the shutdown cooling system from an excessive pressure increase due to PCP starting. When the PCS temperature is above 430°F, the PCS is protected by the primary safety relief valves on the pressurizer. When the secondary side is hotter I than the primary system and the shutdown cooling system is isolated - I from the PCS, the first PCP can be started if the PCS temperature is i controlled and near steady state conditions or if there is a normal I I
bubble in the pressurizer. The revised PCP start criteria are based on analyses referenced in the current technical specifications.
A new limit on operating PCPs P-50A and P-508 together has been added to provide additional acceptable area below the Pressure Temperature limit curves. The limitation on operating P-50A and P-508 together with Tc below 300°F and pressurizer level above 57% allows the Pressure Temperature limits to be 19 psi higher than they would be without this limit. The 57% pressurizer level is not an analytical result, but simply a decision point between having and not having a bubble. It was chosen to agree with the maximum programmed level during power operation.
PCP P-T Limits. 3.1.2, 3.1.3:
The P-T limits were developed using the same general analytical methods used to develop the current limit curves. To make the transition from forced cooling to natural circulation cooling with the shutdown system in operation, the maximum allowed cooldown rate for PCS temperature less than 170°F was increased from 20°F/Hour to
2 40°F/Hour. The existing operating window was maintained by making minor changes in the analysis methodology and by using the ASME code case N-514, Low Temperature Overpressure Protection, to develop the LTOP setpoint curve. The analysis also assumes that a spurious start of the HPSI p~mps is prevented for PCS temperatures below 300°F.
Proposed Specification 3.3.5, which replaces existing Specification 3.3.2.g(l}, requires that both HPSI pumps be rendered incapable of injection into the PCS when below 300°F. That proposed change is discussed in section B, below. Revised Figures 3-1 and 3-2 are provided. Since plant operating procedures only use the limits given in Figures 3-1 and 3-2 for heatup and cooldown operations, Figure 3-3, P-T Limits for Hydro, has been deleted.
The revised P-T calculations also necessitated a change in the minimum temperature for criticality during physics testing, in Specification 3.1.3, from 371°F to 385°F.
In addition to replacing the figures which provide the P-T limits, a more restrictive heatup rate limit is proposed for the pressurizer.
Both the initial issue Palisades Technical Specification 3.l.2e and existing Technical Specification 3.l.2c limit the pressurizer heatup and cooldown rates to 200°F/hour. It has come to our attention that the 200°F/hour heatup rate limit is less conservative than the design calculations for the pressurizer which assume a maximum rate of l00°F/hour. It has been determined that no physical capability exists for heating the pressurizer at a rate even as high as l00°F/hour. The reduced limit is proposed simply to better align the Technical Specifications with the design calculations.
Specification 3.1.2 has been rewritten to provide an Applicability statement and Actions to be taken if the specification is not met.
The existing specification has neither. The proposed Applicability and Actions are taken from LCO 3.4.3 of NUREG 1432, Standard Technical Specifications, Combustion Engineering Plants.
PORV Setting Limit, Figure 3-4:
The new limit curve for the Power Operated Relief Valves was determined using the proposed PCS P-T limit curves and the ASME code case N-514. The analysis accounts for PORV stroke time, mass additions and pressure changes due to temperature increases in the PCS and the pressurizer for an inadvertent SIS. Analyses for other LTOP events were reviewed to ensure that the new limits did not invalidate their conclusions.
B. Revised HPSI Pump restrictions, 3.3.2.g, 4.1.5:
Two changes are proposed for the HPSI pump requirements of existing Specification 3.3.2.g(l}. In addition these HPSI pump requirements have been renumbered so that they are no longer a sub-paragraph of Action statement 3.3.2 and reworded for clarity.
3 Proposed Specification 3.3.4:
Former specifications 3.3.2.g(2) and (3) have been rewritten as proposed specification 3.3.4. The applicability has been revised from 11
>300°F 11 to 11 >325°F. 11 This change in applicability is necessary to allow time during a heatup or cooldown to transition between the requirement to have HPSI pumps operable and the requirement to render HPSI pumps incapable of injection into the PCS. The applicability for the requirement to have two HPSI pumps operable was changed, by Amendment 161, from 325°F to 300°F simply to align all applicability for equipment which is required with the plant hot, but not with the plant cold, with the upper temperature limit of the Shutdown Cooling System (equivalent to changing between Modes 3 and 4 in Standard Technical Specifications). There is no analytical basis for either 300°F or 325°F with respect to HPSI pump operability.
Proposed Specification 3.3.5:
Former specification 3.3.2.g(l) has been rewritten as proposed specification 3.3.5. The applicability has been changed from 11 <260°F 11 to 11 <300°F 11 in accordance with the assumptions of the analysis for the revised P-T limits. A note is proposed to assure that this specification does not cause hesitation in the use of a HPSI pump for PCS makeup if it is needed due to a loss of shutdown cooling of a loss of PCS inventory. The associated surveillance requirement, 4.1.5, has been revised, changing 11 260°F 11 to 11 300°F 11 , accordingly.
II. Analysis of No Significant Hazards Consideration Consumers Power Company finds the activities associated with this proposed Technical Specifications change involve no significant hazards and accordingly, a no significant hazards determination per 10CFR50.92(c) is justified.
The following evaluation supports the finding that operation of the facility in accordance with the proposed Technical Specifications would not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated.
The revision of the Primary Coolant Pump starting limits, PCS P-T curves, and PORV setting limits would not cause any changes to the capability or operation of plant systems that would affect the probability of occurrence or consequences of an accident. These revisions simply update the existing requirements to account for additional reactor vessel fluence.
The reduction of the allowable pressurizer heatup rate would have no effect on operation of the plant. The current limit is physically unobtainable with installed equipment. The proposed change better aligns the Technical Specification limits with the design analysis. The change in the pressurizer heatup rate limit will not increase the probability or consequences of an accident.
Requiring the HPSI pumps to be operable when above 325°F, rather than when above 300°F does not affect the probability or consequences of any accident
4 previously evaluated. Neither the existing 300°F requirement nor the proposed 325°F requirement has an analytical base. This requirement was recently changed from 325°F to 300°F simply for uniformity. With the revised P-T limit analysis requirement to assure that inadvertent HPSI injection will not occur below 300°F, it is necessary to revert to the former limit of 325°F to provide time to transition between these two contrasting HPSI pump requirements.
- 2. Create the possibility of a new or different kind of accident from any previously evaluated.
The revised specifications, PCP starting limits, PCS P-T limits, pressurizer heatup rate, PORV setting limits, and HPSI pump restrictions, all are directly related to, and intended to prevent, a previously analyzed event, failure of the Reactor Coolant Pressure Boundary. Revision of these limits would not create the possibility of a new or different kind of accident.
3; Involve a significant reduction in a margin of safety.
The revised PCP starting limits, PCS P-T limits, and PORV setting limits are calculated using a similar methodology as the limits which they replace. Therefore they provide the same margin of safety.
The revised pressurizer heatup rate reduces the currently allowable limit which is in the direction of increased margin of safety. Since there is no equipment installed which would cause either the existing or the proposed limit to be reached, there will be no change on the operation of the plant equipment. Therefore reducing the limit on the pressurizer heatup rate will not involve a significant reduction in the margin of safety.
Requiring the HPSI pumps to be operable when above 325°F, rather than when above 300°F does not involve a significant reduction in any margin of safety. Neither the existing 300°F requirement nor the proposed 325°F requirement has an analytical base. This requirement was recently changed from 325°F to 300°F simply for uniformity. With the revised P-T limit analysis requirement to assure that inadvertent HPSI injection will not occur below 300°F, it is necessary to revert to the former limit of 325°F to provide time to transition between these two contrasting HPSI pump requirements.
III. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specifications Change Request, entitled "Primary Coolant System Pressure-Temperature Limits",
and has determined that proposing this change does not involve an unreviewed safety question. Further, the change involves no significant hazards consideration. This change has been reviewed by the Nuclear Performance Assessment Department. A copy of this Technical Specifications Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.
5 CONSUMERS POWER COMPANY To the best of my knowledge, the contents of this Technical Specifications change request describing proposed changes to the Primary Coolant System Pressure-Temperature Limits are truthful and complete.
By ~tJ.$ ~
Robert A. Fenech, Vice President Nuclear Operations Sworn and subscribed to before me this /0 day of tfklJJf9-('.J'L 1994.
. Notary Public
&~vu Cc~ Michigan .
My commissio'rl expires ~/4/9')
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