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| {{#Wiki_filter:. . . consumers Power company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 *.1517) 766-0550 February 5, 1985 Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -PROPOSED TECHNICAL SPECIFICATION CHANGE REQUEST -MINIMUM CONDITIONS FOR CRITI.CALITY Attached are three (3) orginals and thirty-seven (37) conformed copies of a Request for Change to the Palisades Technical Specifications. | | {{#Wiki_filter:.. .~ |
| The attached proposed change to the Palisades Technical Specifications provides clarification to the existing Technical Specification 3.1.3.(c). | | consumers Power company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 *.1517) 766-0550 February 5, 1985 Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - PROPOSED TECHNICAL SPECIFICATION CHANGE REQUEST - MINIMUM CONDITIONS FOR CRITI.CALITY Attached are three (3) orginals and thirty-seven (37) conformed copies of a Request for Change to the Palisades Technical Specifications. The attached proposed change to the Palisades Technical Specifications provides clarification to the existing Technical Specification 3.1.3.(c). The proposed change establishes a time constraint of 15 minutes for compliance with Technical Specification 3.l.3(c), which r~flects reasonable operations cqnsiderations. With the reactor critical and the primary coolant temperature below 525°F, the proposed change allows increased operator flexibility by precluding the necessity of immediately bringing the reactor subcritical by control rod insertion. The proposed change is consistent with CE Standard Technical Specifications. |
| The proposed change establishes a time constraint of 15 minutes for compliance with Technical Specification 3.l.3(c), which reasonable operations cqnsiderations. | |
| With the reactor critical and the primary coolant temperature below 525°F, the proposed change allows increased operator flexibility by precluding the necessity of immediately bringing the reactor subcritical by control rod insertion. | |
| The proposed change is consistent with CE Standard Technical Specifications. | |
| A check in the amount of $150.00 is enclosed as required by 10CFR170.21. | | A check in the amount of $150.00 is enclosed as required by 10CFR170.21. |
| Director of Nuclear Licensing CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector | | ~JJ}/~~u}aJL Director of Nuclear Licensing CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector - Palisades 8502120272 850205 PDR ADOCK 05000255 P PDR |
| -Palisades 8502120272 850205 PDR ADOCK 05000255 P PDR TS1184-0001-NL02 | | '-* |
| '-*
| | TS1184-0001-NL02 |
| CONSUMERS POWER COMPANY DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS 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. CHANGE Change Technical Specification 3.l.3(c) to read as follows: c) With the primary coolant temperature below the minimum temperature specified in "a" above, restore the primary coolant temperature to within its limit within 15 minutes, or the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization within the next 15 minutes. II. DISCUSSION Technical Specification 3.1.3, Minimum Conditions for Criticality, establishes a minimum temperature of 525°F for the Primary Coolant System as a requirement for reactor criticality during normal operation. | | |
| Technical Specification 3.1.3 further requires that with the primary coolant temperature below 525°F, the reactor shall be subcritical by an amount equal to or greater than t.he potential reactivity insertion due to depressurization. | | CONSUMERS POWER COMPANY DOCKET 50-255 - LICENSE DPR PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS 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: |
| Contrary to CE Standard Technical Specifications, however, the current Palisades Technical Specifications do not specify a time interval for compliance. | | I. CHANGE Change Technical Specification 3.l.3(c) to read as follows: |
| The above proposed change to the Palisades Technical Specifications provides a reasonable time interval for compliance with Technical Specification 3.l.3(c), and is consistent with CE Standard Technical Specifications. | | c) With the primary coolant temperature below the minimum temperature specified in "a" above, restore the primary coolant temperature to within its limit within 15 minutes, or the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization within the next 15 minutes. |
| Additionally, the proposed change will preclude the necessity of immediately bringing the reactor subcritical by insertion of control rods, which may result in a further temperature decrease. | | II. DISCUSSION Technical Specification 3.1.3, Minimum Conditions for Criticality, establishes a minimum temperature of 525°F for the Primary Coolant System as a requirement for reactor criticality during normal operation. |
| TS1184-0001A-LI01 CONSUMERS POWER COMPANY DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS 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. CHANGE Change Technical Specification 3.l.3(c) to read as follows: c) With the primary coolant temperature below the minimum temperature specified in "a" above, restore the primary coolant temperature to within its limit within 15 minutes, or the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization within the next | | Technical Specification 3.1.3 further requires that with the primary coolant temperature below 525°F, the reactor shall be subcritical by an amount equal to or greater than t.he potential reactivity insertion due to depressurization. Contrary to CE Standard Technical Specifications, however, the current Palisades Technical Specifications do not specify a time interval for compliance. |
| * 15 minutes. II. DISCUSSION Technical Specification 3.1.3, Minimum Conditions for Criticality, establishes a minimum temperature of 525°F for the Primary Coolant System as a requirement for reactor criticality during normal operation. | | The above proposed change to the Palisades Technical Specifications provides a reasonable time interval for compliance with Technical Specification 3.l.3(c), and is consistent with CE Standard Technical Specifications. Additionally, the proposed change will preclude the necessity of immediately bringing the reactor subcritical by insertion of control rods, which may result in a further temperature decrease. |
| Technical Specification 3.1.3 further requires that with the primary coolant temperature below 525°F, the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization. | | TS1184-0001A-LI01 |
| Contrary to CE Standard Technical Specifications, however, the current Palisades Technical Specifications do not specify a time interval for compliance. | | |
| The above proposed change to the Palisades Technical Specifications provides a reasonable time interval for compliance with Technical Specification 3.l.3(c), and is consistent with CE Standard Technical Specifications. | | CONSUMERS POWER COMPANY DOCKET 50-255 - LICENSE DPR PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS 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: |
| Additionally, the proposed change will preclude the necessity of immediately bringing the reactor subcritical by insertion of control rods, which may result in a further temperature decrease. | | I. CHANGE Change Technical Specification 3.l.3(c) to read as follows: |
| TS1184-0001A-LI01 Basis for Determination of No Significant Hazards Considerations We have reviewed the proposed change to allow a 15-minute time constraint for compliance with Technical Specification 3.l.3(c) in order to determine whether or not this change involves a significant hazards consideration. | | c) With the primary coolant temperature below the minimum temperature specified in "a" above, restore the primary coolant temperature to within its limit within 15 minutes, or the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization within the next |
| In our review, we have used the guidance of certain examples (48FR14870). | | * 15 minutes. |
| One of the examples (ii) in this guidance is if a change constitutes an additional limitation, restriction or control not presently included in the Technical Specification, then that change can be considered not likely to involve significant hazards considerations. | | II. DISCUSSION Technical Specification 3.1.3, Minimum Conditions for Criticality, establishes a minimum temperature of 525°F for the Primary Coolant System as a requirement for reactor criticality during normal operation. |
| Since this proposed change adds a 15-minute requirement to 3.l.3(c) which is more limiting than the generic LCO under 3.0.3which allows one (1) hour, we have determined that this change falls within the example and; therefore, the change does not involve a significant hazards consideration. | | Technical Specification 3.1.3 further requires that with the primary coolant temperature below 525°F, the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization. Contrary to CE Standard Technical Specifications, however, the current Palisades Technical Specifications do not specify a time interval for compliance. |
| 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. | | The above proposed change to the Palisades Technical Specifications provides a reasonable time interval for compliance with Technical Specification 3.l.3(c), and is consistent with CE Standard Technical Specifications. Additionally, the proposed change will preclude the necessity of immediately bringing the reactor subcritical by insertion of control rods, which may result in a further temperature decrease. |
| 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 /,@s b,U,<) or R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 5th day of February 1985. Sherry L Durf Notary Puhl Jackson County, Michigan My commission expires November 5, 1986. SHERRY LYNN DURFEY Notary Public, Jackson County, Mich. My Commission Expires Nov. 5, 1986 TS1184-0001B-NL02}} | | TS1184-0001A-LI01 |
| | |
| | Basis for Determination of No Significant Hazards Considerations We have reviewed the proposed change to allow a 15-minute time constraint for compliance with Technical Specification 3.l.3(c) in order to determine whether or not this change involves a significant hazards consideration. In our review, we have used the guidance of certain examples (48FR14870). One of the examples (ii) in this guidance is if a change constitutes an additional limitation, restriction or control not presently included in the Technical Specification, then that change can be considered not likely to involve significant hazards considerations. Since this proposed change adds a 15-minute requirement to 3.l.3(c) which is more limiting than the generic LCO under 3.0.3which allows one (1) hour, we have determined that this change falls within the example and; therefore, the change does not involve a significant hazards consideration. |
| | 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 /,@s b,U,<)or R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 5th day of February 1985. |
| | Sherry L Durf Notary Puhl Jackson County, Michigan My commission expires November 5, 1986. |
| | SHERRY LYNN DURFEY Notary Public, Jackson County, Mich. |
| | My Commission Expires Nov. 5, 1986 TS1184-0001B-NL02}} |
|
|---|
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 company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 *.1517) 766-0550 February 5, 1985 Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - PROPOSED TECHNICAL SPECIFICATION CHANGE REQUEST - MINIMUM CONDITIONS FOR CRITI.CALITY Attached are three (3) orginals and thirty-seven (37) conformed copies of a Request for Change to the Palisades Technical Specifications. The attached proposed change to the Palisades Technical Specifications provides clarification to the existing Technical Specification 3.1.3.(c). The proposed change establishes a time constraint of 15 minutes for compliance with Technical Specification 3.l.3(c), which r~flects reasonable operations cqnsiderations. With the reactor critical and the primary coolant temperature below 525°F, the proposed change allows increased operator flexibility by precluding the necessity of immediately bringing the reactor subcritical by control rod insertion. The proposed change is consistent with CE Standard Technical Specifications.
A check in the amount of $150.00 is enclosed as required by 10CFR170.21.
~JJ}/~~u}aJL Director of Nuclear Licensing CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector - Palisades 8502120272 850205 PDR ADOCK 05000255 P PDR
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TS1184-0001-NL02
CONSUMERS POWER COMPANY DOCKET 50-255 - LICENSE DPR PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS 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. CHANGE Change Technical Specification 3.l.3(c) to read as follows:
c) With the primary coolant temperature below the minimum temperature specified in "a" above, restore the primary coolant temperature to within its limit within 15 minutes, or the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization within the next 15 minutes.
II. DISCUSSION Technical Specification 3.1.3, Minimum Conditions for Criticality, establishes a minimum temperature of 525°F for the Primary Coolant System as a requirement for reactor criticality during normal operation.
Technical Specification 3.1.3 further requires that with the primary coolant temperature below 525°F, the reactor shall be subcritical by an amount equal to or greater than t.he potential reactivity insertion due to depressurization. Contrary to CE Standard Technical Specifications, however, the current Palisades Technical Specifications do not specify a time interval for compliance.
The above proposed change to the Palisades Technical Specifications provides a reasonable time interval for compliance with Technical Specification 3.l.3(c), and is consistent with CE Standard Technical Specifications. Additionally, the proposed change will preclude the necessity of immediately bringing the reactor subcritical by insertion of control rods, which may result in a further temperature decrease.
TS1184-0001A-LI01
CONSUMERS POWER COMPANY DOCKET 50-255 - LICENSE DPR PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS 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. CHANGE Change Technical Specification 3.l.3(c) to read as follows:
c) With the primary coolant temperature below the minimum temperature specified in "a" above, restore the primary coolant temperature to within its limit within 15 minutes, or the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization within the next
II. DISCUSSION Technical Specification 3.1.3, Minimum Conditions for Criticality, establishes a minimum temperature of 525°F for the Primary Coolant System as a requirement for reactor criticality during normal operation.
Technical Specification 3.1.3 further requires that with the primary coolant temperature below 525°F, the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization. Contrary to CE Standard Technical Specifications, however, the current Palisades Technical Specifications do not specify a time interval for compliance.
The above proposed change to the Palisades Technical Specifications provides a reasonable time interval for compliance with Technical Specification 3.l.3(c), and is consistent with CE Standard Technical Specifications. Additionally, the proposed change will preclude the necessity of immediately bringing the reactor subcritical by insertion of control rods, which may result in a further temperature decrease.
TS1184-0001A-LI01
Basis for Determination of No Significant Hazards Considerations We have reviewed the proposed change to allow a 15-minute time constraint for compliance with Technical Specification 3.l.3(c) in order to determine whether or not this change involves a significant hazards consideration. In our review, we have used the guidance of certain examples (48FR14870). One of the examples (ii) in this guidance is if a change constitutes an additional limitation, restriction or control not presently included in the Technical Specification, then that change can be considered not likely to involve significant hazards considerations. Since this proposed change adds a 15-minute requirement to 3.l.3(c) which is more limiting than the generic LCO under 3.0.3which allows one (1) hour, we have determined that this change falls within the example and; therefore, the change does not involve a significant hazards consideration.
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 /,@s b,U,<)or R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 5th day of February 1985.
Sherry L Durf Notary Puhl Jackson County, Michigan My commission expires November 5, 1986.
SHERRY LYNN DURFEY Notary Public, Jackson County, Mich.
My Commission Expires Nov. 5, 1986 TS1184-0001B-NL02
