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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] |
Text
consumers Power David W. Rogers Plant Safety and Licensing Director POWERINli
/llllCHlliAN'S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 April 7, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - TECHNICAL SPECIFICATIONS CHANGE REQUEST - CORE OPERATING LIMITS REPORT A request for a change to the Palisades Technical Specifications (TS) is enclosed. This change is necessary to relocate cycle specific operating limits to a Core Operating Limits Report, which will reduce future need for recurrent changes to the Technical Specifications. While no definitive evaluation of averted cost has been completed, this proposed Technical Specifications change is expected to reduce costs of change request preparation and review. These changes are proposed in accordance with the guidance of Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits From Technical Specifications."
The attached change request provides a description and discussion of each proposed change. In addition to the change request, several attachments have been included to assist the reviewer:
- 1) The Proposed Technical Specifications pages.
- 2) Existing Technical Specifications pages, marked to show the changes.
- 3) The Proposed Core Operating Limits Report It is requested that the Amendment associated with this Technical Specifications change request become effective upon approval.
David W. Rogers Plant Safety and Licensing Director CC Administrator, Region III, USNRC Resident Inspector, Palisades Attachments A 01AS ENERGY COMPANY
CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 It is requested that the Technical Specifications 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. Changes:
It is proposed that the specifications listed below be changed to relocate fuel cycle-specific parameter limits to a Core Operating Limits Report (COLR) in accordance with the guidance of Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits From Technical Specifications." Several of the specification bases are revised to refer to limits relocated to the COLR. In each case where Technical Specification (TS) limits have been rel-ocated to the COLR, the limits placed in the COLR are unchanged and the bases have been revised accordingly. The following changes are proposed:
1.4: A definition for the Core Operating Limits Report is added to the miscellaneous definitions. The proposed definition was taken from NUREG 1432, Standard Technical Specifications, Combustion Engineering Plants (STS).
3.1.lg: The primary coolant Tinlet function with associated inlet temperature limits and the Axial Shape Index limit, Figure 3-0, are relocated to the COLR. Specification 3.1.lg has been revised to include an explicit requirement that ASI be within limits; this is only implied in existing TS. Also an action statement has been added for the condition when reactor inlet temperature is not within limits. The action specified is the same as that specified in STS for Tavg being out of limit. There is currently no action statement provided for inlet temperature being out of limits. The text of Specification 3.1.1 and of its basis have been consolidated to eliminate blank space and unnecessary pages.
3.10.5: The regulating group insertion limits and the control rod insertion limits curve, Figure 3-6, currently in section 3.10.5, have been relocated to the COLR. The action statement, currently part of paragraph 3.10.5a, has been reworded to enhance clarity.
3.10.8: Test exception 3.10.8 has been deleted; it is no longer needed.
3.11.2: The method for determining the Allowable Power Level (currently in the basis) and the Axial Variation Bounding Condition limit, Figure 3.11-1, are relocated to the COLR. Page numbers for Specifications 3.11.2, 3.12, and 3.13 have been revised to eliminate out of sequence page numbering.
3.23.1: The Linear Heat Rate limit, the tables (3.23-1, 3.23-2, 3.23-3),
and Figure 3.23-1 are relocated to the COLR.
3.23.2: The Radial Peaking Factor limits and associated Tables (3.23-2 and 3.23-3) are relocated to the COLR.
6.9.1: An administrative reporting requirement for the COLR is added to the routine reports. The proposed wording is modeled after the wording in STS.
2 II. Discussion The proposed changes relocate limits and parameters that can generally change with core reloads. These values are to be maintained in a Core Operating Limits Report, which will be submitted to the NRC with each change. This amendment request will result in resource savings for Consumers Power Company and the NRC by eliminating routine license amendment requests on changes in values of fuel cycle-specific parameters.
The limits proposed for relocation from the TS to the COLR are required to be developed using NRC-approved methodology. The proposed changes also list the NRC-approved methodology documents in the administrative reporting requirements. In this manner, the calculation methodology and acceptance criteria are referenced in the TS, but not the cycle specific limits. This change will permit specific values to be changed without prior NRC review and approval, but only in accordance with the specified methodologies.
Therefore, a requirement to maintain the plant within the appropriate bounds is retained in the TS. The specific values will be in the COLR.
III. Analysis of No Significant Hazards Consideration Consumers Power Company finds the activities associated with this Technical Specifications (TS) change involve no significant hazards and accordingly, a no significant hazards determination per 10 CFR 50.92(c) is justified.
The following evaluation supports the finding that operation of the facility in accordance with the proposed TS would not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes to the TS simply move the values and parameters for fuel cycle-specific limits from the TS to a Core Operating Limtts Report (COLR). The requirements to maintain the plant within appropriate bounds are retained in the TS. The values of the cycle-specific parameter limits in the COLR are determined using an NRC-approved methodology and remain consistent with all applicable limits of the plant safety analyses that are addressed in the Final Safety Analysis Report (FSAR). A requirement for the COLR and identification of the approved methodology documents are added to the TS. There are no associated changes in plant operation. Therefore, operation of the facility in accordance with the proposed TS would not result in a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Create the possibility of a new or different kind of accident from any previously evaluated.
As discussed above, the proposed changes do not remove or alleviate any requirements to maintain the plant within the appropriate bounds.
There are no associated changes in plant operation. Therefore operation of the facility in accordance with the proposed TS would not create the possibility of a new or different kind of accident from any previously evaluated.
3
- 3. Involve a significant reduction in a margin of safety.
The proposed changes to the TS simply move the values and parameters for cycle-specific limits from the Specifications to a Core Operating Limits Report (COLR). The requirements to maintain the plant within appropriate bounds are retained in the TS. The values of the cycle-specific parameter limits in the COLR are determined using an NRC-approved methodology and remain consistent with all applicable limits of the plant safety analyses that are addressed in the Final Safety Analysis Report (FSAR). A requirement for the COLR and identification of the approved methodology documents are added to the TS. There are no associated changes in plant operation. Therefore, operation of the facility in accordance with the proposed TS would not involve a significant reduction in a margin of safety.
IV. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specifications change request and has determined that 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.
CONSUMERS POWER COMPANY To the best of my knowledge, the contents of this Technical Specifications Change Request are truthful and complete.
By '2Mt1-.£ o~
Robert A. Fenech, Vice President Nuclear Operations Sworn and subscribed to before me this 1 day of --=Gp~.Jtii
. ... """""""1 _ _ 1994.
i~ljyi~
LeAnn Morse, Notary Public Berrien County, Michigan Acting in Van Buren County, Michigan ::: -......:
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My commission expires: February 4, 1997 ....... '
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