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| {{#Wiki_filter:*' .( .. . , . .e CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below: I. Changes Change Section 4.14 in its entirety to read as follows: "4 .14 AUGMENTED INSERVICE INSPECTION PROGRAM FOR STEAM GENERATORS Applicability Applies to the tubes within both steam generators. | | {{#Wiki_filter:*' .( .. . , . .e CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below: I. Changes Change Section 4.14 in its entirety to read as follows: "4 .14 AUGMENTED INSERVICE INSPECTION PROGRAM FOR STEAM GENERATORS Applicability Applies to the tubes within both steam generators. |
| Objective To. provide assurance of continued integrity of the steam generator tubes over their service lifetime. | | Objective To. provide assurance of continued integrity of the steam generator tubes over their service lifetime. |
| Specification | | Specification |
| : 4. 14. 1 General nu0481-0220a-43 Inspections will be made at a frequency of not less than 12 nor more than 24 calendar months after the previous inspection. | | : 4. 14. 1 General nu0481-0220a-43 Inspections will be made at a frequency of not less than 12 nor more than 24 calendar months after the previous inspection. |
| For the purpose of this Technical Specifications, "Tubes" refers to that portion of the steam generator U-tube from the point of entry on the hot leg side completely around the U-bend to the top support of the cold leg, or from the point of entry on the cold leg side to the top support of the cold leg. If inspection of unplugged tubes with ET indications of greater than or equal to 30% (which are obstructed by ET and repair equipment) leads to significant added personnel radiation exposure, alternate tubes may be selected for examination. | | For the purpose of this Technical Specifications, "Tubes" refers to that portion of the steam generator U-tube from the point of entry on the hot leg side completely around the U-bend to the top support of the cold leg, or from the point of entry on the cold leg side to the top support of the cold leg. If inspection of unplugged tubes with ET indications of greater than or equal to 30% (which are obstructed by ET and repair equipment) leads to significant added personnel radiation exposure, alternate tubes may be selected for examination. |
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| 4.14.4 Repair Criteria nu0481-0220a-43 A tube shall require repair when inspection reveals that: (1) Tube degradation exceeds 58% of the tube wall for indications other than multiple ET indications. | | 4.14.4 Repair Criteria nu0481-0220a-43 A tube shall require repair when inspection reveals that: (1) Tube degradation exceeds 58% of the tube wall for indications other than multiple ET indications. |
| If the mean wastage increases over the period since the previous steam generator inspection is less than +1% (essentially no wastage), the operating allowance listed above shall be applicable. | | If the mean wastage increases over the period since the previous steam generator inspection is less than +1% (essentially no wastage), the operating allowance listed above shall be applicable. |
| If the mean wastage increase is greater than or equal to +1%, the NRC shall approve new operating allowance. | | If the mean wastage increase is greater than or equal to +1%, the NRC shall approve new operating allowance. |
| (2) Tube degradation exceeds 35% of the tube wall for multiple ET indications. | | (2) Tube degradation exceeds 35% of the tube wall for multiple ET indications. |
| (3) Passage of a 0.540" ET probe is prohibited. | | (3) Passage of a 0.540" ET probe is prohibited. |
| Acceptable repair techniques for (1) and (2) above are plugging the affected tube or sleeving the tube region *containing the defect. For tubes containing sleeves, the acceptance criteria in Table 4.14.2 shall apply. | | Acceptable repair techniques for (1) and (2) above are plugging the affected tube or sleeving the tube region *containing the defect. For tubes containing sleeves, the acceptance criteria in Table 4.14.2 shall apply. |
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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
- ' .( .. . , . .e CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below: I. Changes Change Section 4.14 in its entirety to read as follows: "4 .14 AUGMENTED INSERVICE INSPECTION PROGRAM FOR STEAM GENERATORS Applicability Applies to the tubes within both steam generators.
Objective To. provide assurance of continued integrity of the steam generator tubes over their service lifetime.
Specification
- 4. 14. 1 General nu0481-0220a-43 Inspections will be made at a frequency of not less than 12 nor more than 24 calendar months after the previous inspection.
For the purpose of this Technical Specifications, "Tubes" refers to that portion of the steam generator U-tube from the point of entry on the hot leg side completely around the U-bend to the top support of the cold leg, or from the point of entry on the cold leg side to the top support of the cold leg. If inspection of unplugged tubes with ET indications of greater than or equal to 30% (which are obstructed by ET and repair equipment) leads to significant added personnel radiation exposure, alternate tubes may be selected for examination.
In any event, unplugged tubes with ET indications greater than or equal to 30% will be inspected within three consecutive inspections.
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- r ! PO'R ADOCK 05000255 1* p ,. PPR t .I t I
. 2 "4.14.2 Inspection Inspection Sample Category A 45%) nu0481-0220a-43 Tubes requiring ET inspection for flaw surveillance are divided into three categories as follows: Category A -This inspection sample .consists of all tubes which contain ET indications greater.than or equal to 45% in either of the previous two inspections.
Category B -This inspection sample consists of a percentage of tubes containing ET indications greater than oi equal to 30% and less than 45% in either of the previous two inspections and do not meet the requirements of Category A. Category C -This inspection sample consists of a random sample of 2% of the unplugged tubes .in the hot leg and 1% of the unplugged tubes in the cold leg in each steam generator.
The tuoes selected to fulfill the Category C examinations shall contain ET indications less than 30% in both the previous two inspections.
In addition, all previously installed sleeves shall be inspected or plugged during each steam generator tube inspection.
Inspection methods shall be qualified for detecting and sizing flaws in all. unblocked tube lengths chosen for inspection.
Table 4.14.1 summarizes the inspection populations and the applicable inspection method. TABLE 4.14.1 Inspection Plan and ET Techniques Inspection Technique Technique A (Equivalent to the Standard .540" dia probe 400 KHz single frequency technique.)
100% of Inspection Sample Technique B Qualified for determining flaw size in the presence of denting in which nique A's results are uninterpretable.
Those tubes in this sample in which Technique A duces uninterpretable results.
c ... .. Inspection Sample "Category B 30% and < 45%) Category C (< 30%) 3 Inspection Technique Technique A 33% of inspection sample. Tubes shall be selected such that a similar percentage of tubes* not previously inspected shall be required until 100% of the Category B sample has been inspected.
Random sample consisting of 2% of the hot leg tubes and 1% of the cold leg tubes. Technique B Those tubes in this sample in which the ET results of Technique A are pretable.
NOTE: Technique B may be used to fulfill Technique.
- A requirements provided that all Technique A requirements are met. 4.14.3 Additional Inspection If the mean wastage increases over the period since the previous steam generator inspection is greater than 2%, 100% of the tubes in Category B above shall be examined.
4.14.4 Repair Criteria nu0481-0220a-43 A tube shall require repair when inspection reveals that: (1) Tube degradation exceeds 58% of the tube wall for indications other than multiple ET indications.
If the mean wastage increases over the period since the previous steam generator inspection is less than +1% (essentially no wastage), the operating allowance listed above shall be applicable.
If the mean wastage increase is greater than or equal to +1%, the NRC shall approve new operating allowance.
(2) Tube degradation exceeds 35% of the tube wall for multiple ET indications.
(3) Passage of a 0.540" ET probe is prohibited.
Acceptable repair techniques for (1) and (2) above are plugging the affected tube or sleeving the tube region *containing the defect. For tubes containing sleeves, the acceptance criteria in Table 4.14.2 shall apply.
Basis 4 "4.14.5 Sleeving Sleeves shall be installed such that, considering the axial location tolerances, swagging does not take place in an area of known degradation.
A baseline ET inspection of all newly installed sleeves shall be performed.
4.14.6 Reporting A steam generator inspection report shall be submitted to the NRG within 90 days of completion of the inspection and. any required repairs. Consumers Power has concluded that the change from coordinated phosphate to volatile chemistry control for the secondary side of the steam ators has reduced the previous corrosion rate to essentially zero. Palisades has not observed any tube leakage since June 1974. more, mean wastage increase.has been essentially zero since since February 1976. The continuing ispection program provides for verifying that the has been arrested.
The inspection program is also consistent with current industry practices and includes.appropriate measures to identify additional degradation of the Palisades steam generators.
Calculations have been performed to demonstrate that a tube uniformly thinned to 36% of its original nominal wall thickness (64% degradation) can withstand a differential pressure of 1380 psid. Likewise, a sleeved tube can withstand the same differential pressure when the limits in Table 4.14.2 are observed.
Combustion Engineering, Inc Report #CEN-59(P) "Palisades Steam Generator Tube Repair by Sleeving," dated August 26, 1977, contains the analytical and test results of tube sleeving.
In dented regions when the presence of a tube support plate tends to cause interference in the eddy current signals, the standard ET tion technique will not be able to detect flaws embedded in these regions. However, there are several advanced inspection probes under development which have been s.hown to be effective in detecting flaws by screening out the interference signals caused by the presence of the tube support plates or dents. nu0481-0220a-43
.. Location Unsleeved Sections Sleeved Section Region 1 ( l) Region 2(2) Region 3C 3) Footnotes: .e "TABLE 4.14.2 Maximum Allowable Degradation Maximum Allowable Degradation(S)
Degradation
= 64% Sleeve degradation
= 34% and tube degradation exceeding the maximum allowable degradation for an unsleeved section. C 4) Either (a) sleeve degradation
= 25% when tube gradation in Region 1 exceeds the maximum allowable degradation for an unsleeved section; or (b) tube degradation to Region 2 equal to the maximum
- allowable degradation for an unsleeved tube. <4) Tube degradation equal to the maximum allowable degradation for an unsleeved section. (l)The undeformed region of the tube/sleeve assembly containing the original imperfection requiring sleeving.
5 (Z)The region containing the expansion joint. Specifically, the region of the tube/sleeve assembly bounded by lines approximately 1/4 inch and 2 inches inboard from the sleeve ends. * (3)The region of the tube/sleeve assembly containing approximately 1/4 inch of each end of the assembly.
- C 4)Degradation occurring in the parent tube at any location in a region and degradation occurring in the sleeve at any location in the same region that exceeds the applicable maximum allowable degradation will require tube plugging. (S)Subtracted from these Maximum Allowable Degradation values shall be an approved operating_
allowance of 6%." nu0481-0220a-43 II. Discussion The Technical Specifications revision is proposed to reflect the unchanging degradation status of the steam generators and improved inspection capabilities.
The two major areas involved in this change request are: A. Modify eddy current test (ET) tube sampling requirements to reflect current steam generator conditions.
B. Establish a standard operating allowance and repair criteria.
6 A summary of current and proposed Technical Specifications requirements is presented in Table 1. As shown in Table 1, the maximum period for reinspection of unplugged tubes containing ET indications greater thazi, or equal to 30% but less than 45% tube wall degradation would be increased from one to three inspection intervals.
Tube sampling would be selected so that 100% of the total sample would be examined within three inspections by a technique qualified for detecting and sizing flaws in the presence of dents. Iri contrast to previous inspections, valid flaw readings were frequently not obtained for indications in this category due to the presence of denting. Inspection and sampling requirements for unplugged ET indications equal to or greater than are unchanged.
The operating allowance is set at 6% by the proposed Technical Specifications, which correlates to a plugging or repair criteria of 58% tube wall degradation for ET indications as was used in previous inspections (maximum allowable tube degradation remains unchanged at for multiple ET indications).
No changes are proposed for sleeved tube inspection sampling or acceptance criteria as shown in Table 4.14.2. NOTE: An editorial change has been made to Footnote 5 of Table 4.14.2. The number of tubes (based on the latest inspection results) which require inspection by various ET techniques under current and proposed Technical Specifications requirements are shown in Table 2. As indicated, the p:r;oposed Technical Specifications should result in a significant increase in the number and percentage of valid ET readings in the greater than or equal to but less than 45% category.
The increase in valid ET readings would be obtained from interpretable inspections of dented intersections achieved by utilization of multifrequency ET equipment and process developments, which were not available previous inspections.
Personnel radiation exposure and time required for ET of the Palisades steam generators is estimated to be reduced by approximately by the proposed Technical Specifications and ET technique developments.
nu0481-0220a-43
.... As concluded in the reports of ET inspections of the Palisades steam generators in 1978 and 1979, adherence to strict secondary water purity limits and the policy of keeping the secondary side in wet lay-up when the steam generators are not operating has essentially stopped the tube corrosion previously experienced.
Therefore, we believe the requested Technical Specifications changes are in accordance with ALARA concepts and also provide the information required to assess the unchanging conditions of the Palisades steam generator tubing. III. Conclusion Based on the foregoing, both the Palisades Plant Review Committee and the Safety and Audit Review Board have reviewed these changes and find them acceptable.
CONSUMERS POWER COMPANY By ynolds, Executive Vice Energy Supply Sworn and subscribed to before me this 2nd day of July 1981. Jackson County, Michigan My commission expires December 14, 1983. nu0481-0220a-43 7
TABLE 1 Summary Comparison of Current and Proposed Tech Spec Requirements (Section 4.14) Requirement ET Inspection Frequency Maximum period for reinspection of unplugged tubes with ET indications greater than or equal to 30% Inspection sample for unplugged tubes containing ET indications equal to or greater than using ET techniques qualified for p.roducing interpretable results Inspection sample for unplugged tubes with ET indications great.er than or equal to. 30% but l.ess than 45% Random sample using pull-through technique for tubes with ET indication less than 30% Operating allowance for multiple ET indications Operating allowance for ET indications other than multiple ET indications Plugging criteria for denting Interval between completion of inspection and repair and mission of inspection report Current Tech Spec Every 12-24 months One inspection (1Wo is allowed if significant crease in radiation exposure results) 100; 2% hot leg 1% cold leg 6% for inspection after 1976 10% for tubes last inspected in 1976 20% for tubes last inspected in 1975 Failure to pass 0.540" probe 30 days 8 Proposed Tech Spec Every 12-24 months Three inspections 100% 33-1/3% NOTE: Chosen so 100% tubes ted within three inspections 2% hot leg 1% cold leg 35% 6% Failure to pass 0.540" probe 90 days NOTE: Sleeve inspection frequency and acceptance criteria unchanged.
nu0481-0220b-43
-**' * ,, ' 1 ,..._
- TABLE 2 Effect on Tubes To Be Inspected of Revised Technical Specifications 9 (Based on Latest Inspection Results From 1979) Inspection Sample Current Tech Spec SG-A SG-B Number of unplugged tubes/ 283/296 214/247 indications with previous ET results equal to or greater than 45% to be inspected Number/percent of unplugged ET indications equal to or greater than 45% which are expected to be given interpretable inspection Number of unplugged tubes/ indications with ET results equal to or greater than 30% but less than 45% to be inspected Number/percent of unplugged ET indications equal to or greater than 30% but less than 45% which are expected to be given an interpretable inspection Tubes included in random sample nu0481-0220c-43 247/100% (Using previous ET techniques) 987/1601 720/1251 1102/68.8%.
716/57.2% (Using previous ET techniques) 132 hot leg 136 hot leg 53 cold leg 69 cold leg Proposed Tech Spec SG-A SG-B 283/296 214/247 296/100% 247/100% (Using new ET techniques) 329/534 240/417 (1/3 (1/3 sample) sample) *534/100%
- 417/100% (Using new techniques)
- 1601 over 3 tions *1251 over *3 tions 132 hot leg 136 hot leg 53 cold leg 69 cold leg