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| {{#Wiki_filter:consumers Power -POW ERi Nii NllCHlliAN'S PROliRESS General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-1636 April 2, 1990 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -TECHNICAL SPECIFICATION CHANGE REQUEST -EDITORIAL CORRECTIONS (TAC NO 76156) Kenneth W Berry Director Nuclear licensing Enclosed is a Technical Specification Change Request which proposes editorial corrections and changes to bring Palisades Technical Specifications in line with the current plant organization. | | {{#Wiki_filter:consumers Power - Kenneth W Berry Director POWERiNii Nuclear licensing NllCHlliAN'S PROliRESS General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-1636 April 2, 1990 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - |
| The change proposes to delete assignment of the functional responsibility for the Industry Operating Experience Review Program from the Technical Specifications.* | | TECHNICAL SPECIFICATION CHANGE REQUEST - EDITORIAL CORRECTIONS (TAC NO 76156) |
| It is Consumers Power Company's intent to maintain responsiblity for this program under the Palisades Plant General Manager. The FSAR will be revised to reflect this responsibility. | | Enclosed is a Technical Specification Change Request which proposes editorial corrections and changes to bring Palisades Technical Specifications in line with the current plant organization. The change proposes to delete assignment of the functional responsibility for the Industry Operating Experience Review Program from the Technical Specifications.* It is Consumers Power Company's intent to maintain responsiblity for this program under the Palisades Plant General Manager. The FSAR will be revised to reflect this responsibility. |
| PQ Berry \)_ -Kenneth W 0 Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector | | PQ |
| -Palisades Attachments | | \)_ - Kenneth W Berry 0 Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachments |
| ' | | ' |
| * 900402 G I I
| | ~-L___.111?1~:.-r;----;o;;ru~:-=,-..~~ G ~I |
| * R **-ADOCI< 0-500.025!5 I * *. * ,: F'DC -.: ,I . OC0390-0305-NL04 A CMS' ENERGY COMPANY \ | | * I |
| 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 the Technical Specifications contained in Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for Palisades Plant be changed as described in Section I below: I. Changes A. Change the first "SV-2412B" for penetration 40B in Table 3.6.1 to "SV-2412A". | | * 0 |
| B. Change "4.20" to 4.21" at the end of Section 3.25.1. C. Revise Section 6.5.3.1 to read as follows: "6.5.3.1 FUNCTION 1 The Plant Safety and Licensing organization shall function to examine proposed changes in design or operation and such other matters as the PRC may assign to identify issues significant to nuclear safety and recommend nuclear safety improvements." D. Change "NSB" to "NSSD" at the end of Section 6.10.2.i by deleting "NSB" and adding "reviews performed by NSSD". II.* Discussion Proposed change A corrects a typographical error made during the issuance of Amendment 128 dated September 5, 1989. Proposed change B corrects a typographical error made during the issuance of Amendment 122 dated 19, 1989. 1 -Proposed change C is requested to lrring Palisades Technical Specifications in line with the cuyrent plant organization. | | ~ 004110082 900402 F~ R **- ADOCI< 0-500.025!5 I **. * ,: |
| When the current Technical Specification wording was approved by the NRC in Amendment 127 dated August 16, 1989, the program to examine nuclear industry operating experience was to be the responsibility of the Plant Safety and Licensing organization. | | F'DC |
| Since that time the responsibility for this program has been reassigned to a newly created organizational unit under the Engineering and Maintenance Manager. TSP0390-0305-NL04 With respect to the examination of nuclear industry operating experience, it is not relevent whethe'r this responsibility is assigned to Plant Safety and Licensing or another organization. | | ~ - .: ,I . |
| It is also not required that Technical Specifications assign this responsibility. | | \ |
| As stated in the NRC Safety Evaluation for Amendment 127, Palisades is not required to have an Independent Safety Engineering Group (ISEG). One of the functions of ISEG, as stated in draft Combustion Engineering Standard Technical Specifications, is to examine operating experience information. | | OC0390-0305-NL04 A CMS' ENERGY COMPANY |
| Accordingly, it is proposed that all reference to the function to examine industry operating experience be deleted from the Palisades Technical Specifications. | | |
| 2 It should be emphasized that deletion of a Technical Specification reference requiring examination of industry operating experience does not imply the function is being eliminated.
| | 1 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 the Technical Specifications contained in Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for Palisades Plant be changed as described in Section I below: |
| Consumers Power Company recognizes this function offers the potential for both safety and financial benefits, and its elimination would be inadvisable. | | I. Changes A. Change the first "SV-2412B" for penetration 40B in Table 3.6.1 to "SV-2412A". |
| It is our intent to maintain this function within the organizational structure. | | B. Change "4.20" to 4.21" at the end of Section 3.25.1. |
| Elimination of reference to this function from the Technical Specifications is also consistent with the intent of the NRC's Technical Specification improvement program to remove organization charts (Generic Letter 88-06) from the Technical Specifications. | | C. Revise Section 6.5.3.1 to read as follows: |
| It allows management flexibility to assign this responsibility as the needs of the organizational structure change. Proposed change D corrects an oversight made during the issuance of Amendment 127 dated August 16, 1989. III. Analysis of No Significant Hazards Consideration These changes as proposed are editorial in nature. Proposed change C will have no practical impact on examination of industry operating experience or safety review functions at the plant or offsite. Assigning the responsibility for industry operating experience review to the Engineering and Maintenance Manager provides more direct feedback to the affected organizations. | | "6.5.3.1 FUNCTION The Plant Safety and Licensing organization shall function to examine proposed changes in design or operation and such other matters as the PRC may assign to identify issues significant to nuclear safety and recommend nuclear safety improvements." |
| The changes have no effect on the probability of occurrence or consequences of an accident, nor has the possibility of an accident or malfunction of a different type been created because they do not effect the plant configuration nor the plant operating requirements. | | D. Change "NSB" to "NSSD" at the end of Section 6.10.2.i by deleting "NSB" and adding "reviews performed by NSSD". |
| | II.* Discussion Proposed change A corrects a typographical error made during the issuance of Amendment 128 dated September 5, 1989. |
| | Proposed change B corrects a typographical error made during the issuance of Amendment 122 dated Ma~ 19, 1989. |
| | 1 - |
| | :~~ |
| | Proposed change C is requested to lrring Palisades Technical Specifications in line with the cuyrent plant organization. When the current Technical Specification wording was approved by the NRC in Amendment 127 dated August 16, 1989, the program to examine nuclear industry operating experience was to be the responsibility of the Plant Safety and Licensing organization. Since that time the responsibility for this program has been reassigned to a newly created organizational unit under the Engineering and Maintenance Manager. |
| | TSP0390-0305-NL04 |
| | |
| | 2 With respect to the examination of nuclear industry operating experience, it is not relevent whethe'r this responsibility is assigned to Plant Safety and Licensing or another organization. It is also not required that Technical Specifications assign this responsibility. As stated in the NRC Safety Evaluation for Amendment 127, Palisades is not required to have an Independent Safety Engineering Group (ISEG). One of the functions of ISEG, as stated in draft Combustion Engineering Standard Technical Specifications, is to examine operating experience information. Accordingly, it is proposed that all reference to the function to examine industry operating experience be deleted from the Palisades Technical Specifications. |
| | It should be emphasized that deletion of a Technical Specification reference requiring examination of industry operating experience does not imply the function is being eliminated. Consumers Power Company recognizes this function offers the potential for both safety and financial benefits, and its elimination would be inadvisable. It is our intent to maintain this function within the organizational structure. |
| | Elimination of reference to this function from the Technical Specifications is also consistent with the intent of the NRC's Technical Specification improvement program to remove organization charts (Generic Letter 88-06) from the Technical Specifications. It allows management flexibility to assign this responsibility as the needs of the organizational structure change. |
| | Proposed change D corrects an oversight made during the issuance of Amendment 127 dated August 16, 1989. |
| | III. Analysis of No Significant Hazards Consideration These changes as proposed are editorial in nature. Proposed change C will have no practical impact on examination of industry operating experience or safety review functions at the plant or offsite. |
| | Assigning the responsibility for industry operating experience review to the Engineering and Maintenance Manager provides more direct feedback to the affected organizations. The changes have no effect on the probability of occurrence or consequences of an accident, nor has the possibility of an accident or malfunction of a different type been created because they do not effect the plant configuration nor the plant operating requirements. |
| The margin of safety as defined in the basis for the Technical Specifications will not be affected because no margin of safety is defined for the Administrative Controls Section of the Technical Specifications, and the proposed changes are editorial corrections. | | The margin of safety as defined in the basis for the Technical Specifications will not be affected because no margin of safety is defined for the Administrative Controls Section of the Technical Specifications, and the proposed changes are editorial corrections. |
| TSP0390-0305-NL04 IV. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined this change does 3 not involve an unreviewed safety question and, therefore, involves no significant hazards consideration. | | TSP0390-0305-NL04 |
| This change has been reviewed by the Nuclear Safety Services Department. | | |
| 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 To the best of my knowledge, information and belief, the contents of this Technical Specification Change Request are truthful and complete. | | 3 IV. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined this change does not involve an unreviewed safety question and, therefore, involves no significant hazards consideration. This change has been reviewed by the Nuclear Safety Services Department. 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. |
| __ _ Nuclear Operations Sworn and subscribed to before me this 2nd day of April 1990. | | CONSUMERS POWER COMPANY To the best of my knowledge, information and belief, the contents of this Technical Specification Change Request are truthful and complete. |
| | By~p~~e-n_t _ __ |
| | Nuclear Operations Sworn and subscribed to before me this 2nd day of April 1990. |
| | ~l~/ |
| Elaine E Buehrer, Notary Public Jackson County, Michigan My commission expires October 11, 1993 TSP0390-0305-NL04}} | | Elaine E Buehrer, Notary Public Jackson County, Michigan My commission expires October 11, 1993 TSP0390-0305-NL04}} |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
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consumers Power - Kenneth W Berry Director POWERiNii Nuclear licensing NllCHlliAN'S PROliRESS General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-1636 April 2, 1990 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
TECHNICAL SPECIFICATION CHANGE REQUEST - EDITORIAL CORRECTIONS (TAC NO 76156)
Enclosed is a Technical Specification Change Request which proposes editorial corrections and changes to bring Palisades Technical Specifications in line with the current plant organization. The change proposes to delete assignment of the functional responsibility for the Industry Operating Experience Review Program from the Technical Specifications.* It is Consumers Power Company's intent to maintain responsiblity for this program under the Palisades Plant General Manager. The FSAR will be revised to reflect this responsibility.
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\)_ - Kenneth W Berry 0 Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachments
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OC0390-0305-NL04 A CMS' ENERGY COMPANY
1 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 the Technical Specifications contained in Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for Palisades Plant be changed as described in Section I below:
I. Changes A. Change the first "SV-2412B" for penetration 40B in Table 3.6.1 to "SV-2412A".
B. Change "4.20" to 4.21" at the end of Section 3.25.1.
C. Revise Section 6.5.3.1 to read as follows:
"6.5.3.1 FUNCTION The Plant Safety and Licensing organization shall function to examine proposed changes in design or operation and such other matters as the PRC may assign to identify issues significant to nuclear safety and recommend nuclear safety improvements."
D. Change "NSB" to "NSSD" at the end of Section 6.10.2.i by deleting "NSB" and adding "reviews performed by NSSD".
II.* Discussion Proposed change A corrects a typographical error made during the issuance of Amendment 128 dated September 5, 1989.
Proposed change B corrects a typographical error made during the issuance of Amendment 122 dated Ma~ 19, 1989.
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Proposed change C is requested to lrring Palisades Technical Specifications in line with the cuyrent plant organization. When the current Technical Specification wording was approved by the NRC in Amendment 127 dated August 16, 1989, the program to examine nuclear industry operating experience was to be the responsibility of the Plant Safety and Licensing organization. Since that time the responsibility for this program has been reassigned to a newly created organizational unit under the Engineering and Maintenance Manager.
TSP0390-0305-NL04
2 With respect to the examination of nuclear industry operating experience, it is not relevent whethe'r this responsibility is assigned to Plant Safety and Licensing or another organization. It is also not required that Technical Specifications assign this responsibility. As stated in the NRC Safety Evaluation for Amendment 127, Palisades is not required to have an Independent Safety Engineering Group (ISEG). One of the functions of ISEG, as stated in draft Combustion Engineering Standard Technical Specifications, is to examine operating experience information. Accordingly, it is proposed that all reference to the function to examine industry operating experience be deleted from the Palisades Technical Specifications.
It should be emphasized that deletion of a Technical Specification reference requiring examination of industry operating experience does not imply the function is being eliminated. Consumers Power Company recognizes this function offers the potential for both safety and financial benefits, and its elimination would be inadvisable. It is our intent to maintain this function within the organizational structure.
Elimination of reference to this function from the Technical Specifications is also consistent with the intent of the NRC's Technical Specification improvement program to remove organization charts (Generic Letter 88-06) from the Technical Specifications. It allows management flexibility to assign this responsibility as the needs of the organizational structure change.
Proposed change D corrects an oversight made during the issuance of Amendment 127 dated August 16, 1989.
III. Analysis of No Significant Hazards Consideration These changes as proposed are editorial in nature. Proposed change C will have no practical impact on examination of industry operating experience or safety review functions at the plant or offsite.
Assigning the responsibility for industry operating experience review to the Engineering and Maintenance Manager provides more direct feedback to the affected organizations. The changes have no effect on the probability of occurrence or consequences of an accident, nor has the possibility of an accident or malfunction of a different type been created because they do not effect the plant configuration nor the plant operating requirements.
The margin of safety as defined in the basis for the Technical Specifications will not be affected because no margin of safety is defined for the Administrative Controls Section of the Technical Specifications, and the proposed changes are editorial corrections.
TSP0390-0305-NL04
3 IV. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined this change does not involve an unreviewed safety question and, therefore, involves no significant hazards consideration. This change has been reviewed by the Nuclear Safety Services Department. 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 To the best of my knowledge, information and belief, the contents of this Technical Specification Change Request are truthful and complete.
By~p~~e-n_t _ __
Nuclear Operations Sworn and subscribed to before me this 2nd day of April 1990.
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Elaine E Buehrer, Notary Public Jackson County, Michigan My commission expires October 11, 1993 TSP0390-0305-NL04