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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
[Table view] |
Text
consumers Power KurtM. Haas Plant Safety and Licensing Director l'OWERINli MICHlliAN"S PROliRE55 Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 July 5, 1995 U S Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT TECHNICAL SPECIFICATIONS CHANGE REQUEST - ADMINISTRATIVE CONTROLS A request for a change to the Palisades Technical Specifications is enclosed.
The proposed changes all pertain to the Administrative Controls Section of the
. Technical Specifications. The changes involve the following:
A. Deletion of Section 6.4, TRAINING, which is redundant to the requirements in 10CFR55.
B. Revision of Section 6.5.1.2, on the Plant Review Committee Composition, to clarify the membership and designation of members in the administrative procedures.
C. Revision to Sections 6.5.3.1 and 6.5.3.2, to clarify and modify the Function and Composition of the Plant Safety and Licensing staff review requirements.
SUMMARY
OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.
Kurt M. Haas, Plant Safety and Licensing Director CC Administrator, Region III, USNRC Project Manager, NRR, USNRC Resident Inspector, USNRC - Palisades State of Michigan Attachments 9507110249 950705 - - '
PDR ADOCK 05000255 P PDR
.::.. ..;,._ l, \.i ~.. ":!
A CMS' ENERGY COMPANY
CONSUMERS POWER COMPANY Docket 50~255 Request for Change to the Technical Specifications License DPR-20 It is requested that the Technical Specifications contained in the Facility Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on February 21, 1991 for the Palisades Plant, be changed as described below:
I. Changes It is proposed that specification 6.4, Training, be deleted from the Technical Specifications Administrative Controls section. This proposal is an administrative change that will correct an out-of-date statement in the specifications. The change is also consistent with Revision 1, dated April 7, 1995, of the Combustion Engineering Owners Group Standard Technical Specifications, NUREG-1432, which has similarly removed the corresponding Training section from the specifications.
It is also proposed that specifications 6.5.1.2, Plant Review Committee Composition; 6.5.3.1, Plant Safety and Licensing Function; and 6.5.3.2, Plant Safety and Licensing Composition, be changed to reflect the present plant organization, specifically require PRC membership be described in the plant Administrative Procedures, clarify the review function, and delete the specific staff size for the Plant Safety and Licensing staff. These changes are administrative and, in part, remove descriptions that require periodic revision as plant organizations change. Revising these descriptions to permit organization changes is burdensome to both the NRC and plant staff.
II. Discussion of Proposed Changes The change to remove Section 6.4, Training, will correct an out-of-date statement in the specifications. The specification refers td Appendix "A" of 10 CFR Part 55 which has been removed from the regulations.
Appendix "A" of 10CFR55 previously addressed operator requalification.
These requirements have been incorporated into paragraph 55.59 and in other supporting paragraphs. Any regulation in 10 CFR is sufficient in its requirements such that regulation compliance need not be reiterated in the Technical Specifications. Stipulating in the Technical Specifications that a regulation must be followed creates a redundant requirement that adds no value, and causes an administrative burden to the utility and to the NRC in making changes. As a result, NUREG 1432 was revised on April 7, 1995 and the corresponding "Training" section, previously in the Standard Technical Specifications, was removed.
Palisades, like other United States nuclear utilities, has training programs that are accredited by the National Academy for Nuclear Training Accreditation Board. There are twelve Accredited Training Programs at Palisades; six i.n Operations, Chemistry, Health Physics, Electrical, Mechanical, Instrument and Control and Engineering Support.
These programs meet or exceed the training requirements presently specified in Technical Specifications Section 6.4 and are controlled through our administrative processes.
2 Removal of Technical Specifications Section 6.4 will also result in deletion of a statement that " ... training program for the plant staff shall be maintained and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI NlB.1-1971 . . . " . Section 5.5 of this ANSI Standard, Retraining and Replacement Training, describes, in general, the training program scope. These guidelines are met or exceeded by 10CFR55 requirements. Therefore, removal of the reference to the ANSI standard will not reduce the training requirements for the operations staff. In addition, by reference to ANSI NlB.1-1971 in Section 6.3.1 of the Palisades Technical Specifications, the plant staff, including the operations staff, will continue to meet or exceed these minimum staff qualifications.
The remaining portion of the proposed Technical Specifications change addresses the Administrative Controls for the composition of the Palisades on-site review committee, the Plant Review Committee (PRC),
and the composition of the Plant Safety and Licensing organization which functions to review proposed plant changes on behalf of the PRC. The change. to the PRC Section 6.5.1.2, COMPOSITION, is administrative and does not affect the present composition in any manner. It clarifies the makeup of the PRC by removing descriptive words that could be
- misinterpreted as to what comprises the plant staff. Prior*to the present organization, plant staff members were diff~rentiated from the engineering organization (NECO) and reported to the Plant General
- Manager. With the present Palisades site organization under the onsite Vice President, the site staffs reporting to the Plant General Manager, Engineering and Modifications Manager, Plant Safety and Licensing Director, and Nuclear Services Manager are all considered plant staff.
Differentiation of the plant staff from the engineering (NECO) staff in the Technical Specifications is no longer appropriate. Furthermore, the engineering organization has reorganized and has been renamed as the Engirieering and Modifications Department, but has also retained the NECO designation because that name still appears in this Technical Specification. It is no longer desirable to maintain the NECO name.
It is also proposed that Section 6.5.1.2, COMPOSITION, be altered by requiring the chairman, alternate chairmen, and members of the PRC to be designated in administrative procedures by the Plant General Manager.
At present the designation of the chairman and alternate chairmen is made in memorandum form by the Plant General Manager, and only the members are listed in the administrative procedures. This proposed change will consolidate the requirements and provide the appropriate controls for designating the PRC membership. Like the other changes to this section, this is an administrative change.
The proposed change to the Plant Safety and Licensing Section 6.5.3.1, FUNCTION, provides an administrative change in the description of the organization function. Changes to Section 6.5.3.2, COMPOSITION, clarify that only those members of the Plant Safety and Licensing staff responsible for the review function described in the Technical Specifications must meet the qualifications in Section 6.3. The Plant Safety and Licensing department has several different functions. These
3 functions include those described in the Technical Specifications, as well as several other functions not described in the Technical Specifications which have different qualification requirements. T~is proposed change imp~icitly recognizes that these other functions exist.
This proposed change, to Section 6.5.3.2, also removes the stipulation that the Plant Safety and Licensing staff have at least five persons qualified to conduct the reviews delegated to them. In the original conception of the department review responsibilities, a minimum staff of five members was considered as necessary. In practice, however, even
.though five individuals in the Plant Safety and Licensing staff have remained qualified to conduct the reviews on behalf of the Plant Review Committee, nearly all the reviews have been handled by three individuals. In addition, we consider the number of persons necessary to conduct these reviews to be a matter to be handled administratively, as it can fluctuate with the workload. Therefore, the number of Plant Safety and Licensing individuals qualified to perform the reviews is not specified in this proposed change.
The proposed change to Section 6.5.3.2 also removes the title to which the Plant Safety and Licensing staff reports; the Plant Safety and Licensing Director. This, too, is considered as an unnecessary Technical Specifications administrative requirement as the titles of personnel can be changed quite frequently. Titles should be strictly under the control of the licensee. Furthermore, the NRC staff guidance has been to remove items such as these which frequently change and cause unnecessary burden on both the Palisades staff, and especially the NRC staff, in reviewing and issuing of an amendment. There is no present intent to transfer the Plant Safety and Licensing review function from under the Plant Safety and Licensing Director to some other department in which documents requiring PRC review are originated. However, departmental independence is not considered a necessity to assure quality reviews by the Plant Safety and Licensing staff.
III. Analysis of No Significant Hazards Consideration Consumers Power Company finds the activities associated with this Technical Specifications change in compliance with IOCFR50.92(c) and that a no significant hazards determination is justified. The following evaluation supports the finding that operation of the facility in accordance with the proposed Technical Specifications would not:
A. Involve a significant increase in the probability or consequences of an accident previously evaluated.
This change does not affect the probability or consequences of an accident. The changes are administrative; deleting an unnecessary specification on staff training requirements, eliminating the specific references to the Nuclear Engineering and Construction Organization (NECO) staff, and requiri~g that the Plant Review Committee (PRC) chairman, alternate chairman~ and members be designated in administrative procedures by the Plant General
4 Manager. Further administrative changes clarify the function of the Plant Safety and Licensing organization and ~liminate the numerical requirement for five staff members to fulfill the organization function.
The removal of an obsolete staff training requirement does not diminish the regulatory requirement to have an adequately trained staff. The accredited training programs for the plant staff ensure an appropriate level of training is conducted to maintain an appropriate skill and knowledge base for the staff. The requirements of 10CFR55 provide the necessary rules for operator licenses. Since a trained staff will be maintained, there will no increase in the probability or consequences of an accident as a result of this change.
The composition of the PRC will not be affected by this change as it will, at a minimum, be comprised of personnel from the operations, engineering, radiological services and maintenance departments as required by the Technical Specifications. The composition of the Plant Safety and Licensing organization as a whole may change. The function of the organization as it relates to these Technical Specifications, however, will not be affected.
These changes have no affect on the plant accident analyses.
Qualified personnel will continue to conduct the PRC and Plant Safety and Licensing reviews. Therefore, the changes ~o not increase the probability or consequences of an accident.
B. Create the possibility of a new or different kind of accident from any previously evaluated.
The proposed changes are administrative and do not create the possibility of a new or different kind of accident. Staff training will continue to meet the accreditation requirements of the National Academy for Nuclear Training Accreditation Board and the requirements for the Systematic Approach to Training.
Operators' license training will continue to meet the regulatory requirements of IOCFR55. Activities conducted by the Plant Review Committee and the Plant Safety and Licensing staff will continue to be accomplished by a staff which meets the qualifi~ation requirements of the Technical Specifications. These admi ni strati ve changes wil 1 not affect the operation of the p1ant or the safety function of plant equipment nor will it affect the quality of the review activities. Therefore, there will be no possibility that a new or different kind of accident will be created.
C. Involve a significant reduction in a margin of safety.
The changes do not affect installed plant equipment nor do they affect *plant operations. These administrative changes have not affected the probability or consequences of a previously analyzed
5 accident or created the possibility of a new or different kind or accident from any previously evaluated. Therefore, they do not involve any reduction in the margin of safety.
IV. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specifications change request and has determined that the change involves no significant hazards consideration. This change has been reviewed by the Nuclear Performance Assessment Department. A copy of this Technical Specifications change request has been sent to the State of Michigan.
CONSUMERS POWER COMPANY To the best of my knowledge, the contents of this Facility Operating License and Technical Specifications change request, proposing changes to the Administrative Controls section, are truthful and complete.
By ----~~- v_V~--:L_-'-=-"'~=----.:..__
l1fdriiaS J. Palmisano Plant General Manager Sworn and subscribed to before me this _fi_ day of~ 1995.
L_~~~
LeAnn Morse, Notary Public Berrien County, Michigan (Acting in Van Buren County, Michigan)
My commission expires February 4, 1997
...~ - 'I 1** I *