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| {{#Wiki_filter:* ..* *, !). * ( I consumers Power POW ERi Nii NllCHlliAN'S PROliRESS | | {{#Wiki_filter:,* |
| ,* Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 May 30, 1991 Nu cl ear Regulatory Commi ss.i on Document Control Desk Washingttin, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT 7 GB Slade General Manager TECHNICAL SPECIFICATIONS CHANGE REQUEST -VARIABLE HIGH POWER TRIP SETPOINT CHANGE Enclosed is a request for change to the Palisades Technical to incorporate a changeto the reactor variable high power trip setpoint.
| | *..* *, |
| *Attachment 1 of this submjttal contains the proposed Technical Spectfications pages and Attachment 2 has the exist i.ng Technical Specifications pages marked to show the proposed changes. | | !). |
| 3, provided for your is a copy of ANF-90-181, "Review and Analyses of Standard Review Plan Chapter 15 events for Palisades with a 15% Variable High Power Trip Reset." It is re_quested. | | * consumers Power GB Slade General Manager POWERiNii NllCHlliAN'S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 May 30, 1991 Nu cl ear Regulatory Commi ss.i on Document Control Desk Washingttin, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT 7 TECHNICAL SPECIFICATIONS CHANGE REQUEST - VARIABLE HIGH POWER TRIP SETPOINT CHANGE Enclosed is a request for change to the Palisades Technical Specification~ to incorporate a changeto the reactor variable high power trip setpoint. |
| that this change be made effective upon. issuance. Gerald B*Slade General Manager CC: | | *Attachment 1 of this submjttal contains the proposed Technical Spectfications pages and Attachment 2 has the exist i.ng Technical Specifications pages marked |
| Region Ill, USNRC NRC Resident Inspector, Palisades Attachments 91061800Cl:3-9TOS3-C1 PDR AOOCK 05000255 P . . PDR _! A CMS' ENER5Y COMPANY | | ~P to show the proposed changes. Att~chment 3, provided for your infor~ation, is a copy of ANF-90-181, "Review and Analyses of Standard Review Plan Chapter 15 events for Palisades with a 15% Variable High Power Trip Reset." It is re_quested. that this change be made effective upon. issuance. |
| ,..., .. , a. Uncontrolled Control Bank Withdrawal at Power 14.2.2 MDNBR-1.420. b. Control Rod Mis-operation 14.2.3 MDNBR-1.197. | | ~ |
| In both events the Minimum Departure from Nucleate Boiling Ratio (MDNBR) was greater than the Technical Specification Limit for Cycle 9 (1.190 for Kand L fuel, and 1.174 for M fuel) and only changed by -1.5% and -4.0% respectively from the previous analysis (ANF-90-078). | | Gerald B*Slade General Manager CC: Administrator~ Region Ill, USNRC NRC Resident Inspector, Palisades Attachments |
| The purpose of making this set point change is to eliminate unnecessary plant trips following a rapid power reduction from high power levels. Near beginning of cycle (BOC) conditions, the positive reactivity feedback due to a S/G overcooling event, can increase the core power more than 10% above the minimum power level as steady state conditions are reached. By changing the VHPT from 10% to 15%, reactor trips could be avoided thereby, not putting the plant through unnecessary transients. | | ( 91061800Cl:3-9TOS3-C1 I |
| The higher delta-power of 15% is still low enough to provide the minimum departure from nucleate boiling (MDNB) margins required for all other affected transients. | | PDR AOOCK 05000255 P . . PDR A CMS' ENER5Y COMPANY |
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| | ,...,. , |
| | : a. Uncontrolled Control Bank Withdrawal at Power 14.2.2 MDNBR-1.420. |
| | : b. Control Rod Mis-operation 14.2.3 MDNBR-1.197. |
| | In both events the Minimum Departure from Nucleate Boiling Ratio (MDNBR) was greater than the Technical Specification Limit for Cycle 9 (1.190 for Kand L fuel, and 1.174 for M fuel) and only changed by -1.5% and -4.0% respectively from the previous analysis (ANF-90-078). The purpose of making this set point change is to eliminate unnecessary plant trips following a rapid power reduction from high power levels. Near beginning of cycle (BOC) conditions, the positive reactivity feedback due to a S/G overcooling event, can increase the core power more than 10% above the minimum power level as steady state conditions are reached. |
| | By changing the VHPT from 10% to 15%, reactor trips could be avoided thereby, not putting the plant through unnecessary transients. The higher delta-power of 15% is still low enough to provide the minimum departure from nucleate boiling (MDNB) margins required for all other affected transients. |
| : 2. Create the possibility of a new or different kind of accident from any previously evaluated. | | : 2. Create the possibility of a new or different kind of accident from any previously evaluated. |
| The proposed technical specification change does not create the. possibility of a new or different kind of accident from any previously evaluated. | | The proposed technical specification change does not create the. |
| The VHPT set point is used to define the radial peaking factors as a function of power that are used in the generation of the core protection limits for the thermal margin/low pressure (TM/LP). ANF-90-181 contains ANF's disposition of Chapter 15 analysis which identifies the events that. are impacted by the proposed increase. | | possibility of a new or different kind of accident from any previously evaluated. The VHPT set point is used to define the radial peaking factors as a function of power that are used in the generation of the core protection limits for the thermal margin/low pressure (TM/LP). ANF-90-181 contains ANF's disposition of Chapter 15 analysis which identifies the events that. are impacted by the proposed increase. SRP events 15.4.2, and 15.4.3 are the only two events that were identified requiring reanalysis. The plant hardware was not changed and the plant operating conditions were not changed. |
| SRP events 15.4.2, and 15.4.3 are the only two events that were identified requiring reanalysis. | | : 3. Involve a significant reduction in the margin of safety. |
| The plant hardware was not changed and the plant operating conditions were not changed. 3. Involve a significant reduction in the margin of safety. The margin of safety as defined by plant licensing bases is not s i gn'i f i cant l y reduced by the proposed technical spec if i cation change. The proposed technical specification maintains 95% probability, at a 95% confidence level, that departure from nucleate boiling (DNB) will not occur for all reactivity insertion transient calculations. | | The margin of safety as defined by plant licensing bases is not s i gn'i f i cant l y reduced by the proposed technical spec if i cation change. The proposed technical specification maintains 95% |
| Plant safety also may be increased by reducing the potential for unnecessary plant trips. | | probability, at a 95% confidence level, that departure from nucleate boiling (DNB) will not occur for all reactivity insertion transient calculations. Plant safety also may be increased by reducing the potential for unnecessary plant trips. |
| 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 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 in Section I below: I. Changes A. In Table 2.3.1, "Reactor Protection System Trip Setting Limits," revise both the four and three primary coolant pumps operation "Variable High Power" set point from 10% above core power," to 15% above core power." B. In 2.3, "Basis," Item 1, change the first full paragraph as indicated in Attachment | | |
| : 2. In the second full paragraph of the same section, change the footnote as indicated in Attachment
| | 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 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 in Section I below: |
| : 2. Also change Reference 1 from "ANF-90-078, Table 15.0.7-1" to "ANF-90-181, Section 15.0.7." and change Reference 4 from "ANF-90-078, Section 15.0.7-1" to "ANF-90-078, Section 15.0.7". II. Discussion Description of Item The variable high power trip'(VHPT) is incorporated in the reactor protection system (RPS) to provide a reactor trip for transients exhibiting a core power increase from any initial power level. The variable high power function is enabled at approximately 30% power with the current variable trip reset margin set at 10%. The proposed technical specification changes the variable trip reset margin to 15%. III. Analysis of No Significant Hazards Consideration Consumers Power Company finds that activities associated with this proposed Technical Specifications change involve no significant hazards; and accordingly, a no significant hazards determination per 10CFR50.92(c) is justifted.
| | I. Changes A. In Table 2.3.1, "Reactor Protection System Trip Setting Limits," revise both the four and three primary coolant pumps operation "Variable High Power" set point from "~ 10% above core power," to "~ 15% above core power." |
| The following evaluation supports the finding that the proposed changes would not: 1. Involve a significant increase in the possibility or consequences of an accident previously evafoated. | | B. In 2.3, "Basis," Item 1, change the first full paragraph as indicated in Attachment 2. In the second full paragraph of the same section, change the footnote as indicated in Attachment 2. |
| The proposed technical specification changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. | | Also change Reference 1 from "ANF-90-078, Table 15.0.7-1" to "ANF-90-181, Section 15.0.7." and change Reference 4 from "ANF-90-078, Section 15.0.7-1" to "ANF-90-078, Section 15.0.7". |
| Advanced Nuclear Fuels (ANF)-90-181, "Review and Analysis of Standard Review Plan (SRP) Chapter 15 Events for Palisades with a 15% Variable High Power Trip Reset", is the safety analysis that bounds the proposed technical specification change. Two events were re-analyzed for increasing the variable trip set point from 10% -15%; [ | | II. Discussion Description of Item The variable high power trip'(VHPT) is incorporated in the reactor protection system (RPS) to provide a reactor trip for transients exhibiting a core power increase from any initial power level. The variable high power function is enabled at approximately 30% power with [ |
| , I* | | the current variable trip reset margin set at 10%. The proposed technical specification changes the variable trip reset margin to 15%. |
| * III. Conclusion The Palisades Plant Review.Committee has reviewed this Technical Specifications Change Request and*has determined'that
| | III. Analysis of No Significant Hazards Consideration Consumers Power Company finds that activities associated with this proposed Technical Specifications change involve no significant hazards; and accordingly, a no significant hazards determination per 10CFR50.92(c) is justifted. The following evaluation supports the finding that the proposed changes would not: |
| *this* change -does not involve.an unreviewed safety question. | | : 1. Involve a significant increase in the possibility or consequences of an accident previously evafoated. |
| Further, the change involves no significant hazards This change | | The proposed technical specification changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. Advanced Nuclear Fuels (ANF)- |
| * has been .reviewed by the Nuclear Safety Services Department. | | 90-181, "Review and Analysis of Standard Review Plan (SRP) |
| A copy of this Technical Specifications 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 Specifications Change Request are truthful and complete. | | Chapter 15 Events for Palisades with a 15% Variable High Power Trip Reset", is the safety analysis that bounds the proposed technical specification change. Two events were re-analyzed for increasing the variable trip set point from 10% - 15%; |
| * Sworn and' subscribed to* before* me this 4th day* of _*_J_u_n_e | | |
| ____ 1991. LeAnn Morse, Notary Public Van Buren Co, Michigan 'My June [eANN MORSE, NOTARY PUBLIC *VAN BUREN COUNTY, STATE OF MICHIGAN ' MY COMMISSION EXPIRES 06-06**94 . 6' 1994}}
| | , |
| | * I* |
| | III. Conclusion The Palisades Plant Review.Committee has reviewed this Technical Specifications Change Request and*has determined'that *this* change |
| | - does not involve.an unreviewed safety question. Further, the change involves no significant hazards consi~eration. This change |
| | * has been .reviewed by the Nuclear Safety Services Department. A copy of this Technical Specifications 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 Specifications Change Request are truthful and complete. |
| | * Sworn and' subscribed to* before* me this 4th day* of _*_J_u_n_e_ _ _ _ 1991. |
| | [eANN MORSE, NOTARY PUBLIC |
| | *VAN BUREN COUNTY, STATE OF MICHIGAN LeAnn Morse, Notary Public ' MY COMMISSION EXPIRES 06-06**94 . |
| | Van Buren Co, Michigan |
| | 'My commission*expires~ June 6' 1994}} |
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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 GB Slade General Manager POWERiNii NllCHlliAN'S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 May 30, 1991 Nu cl ear Regulatory Commi ss.i on Document Control Desk Washingttin, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT 7 TECHNICAL SPECIFICATIONS CHANGE REQUEST - VARIABLE HIGH POWER TRIP SETPOINT CHANGE Enclosed is a request for change to the Palisades Technical Specification~ to incorporate a changeto the reactor variable high power trip setpoint.
- Attachment 1 of this submjttal contains the proposed Technical Spectfications pages and Attachment 2 has the exist i.ng Technical Specifications pages marked
~P to show the proposed changes. Att~chment 3, provided for your infor~ation, is a copy of ANF-90-181, "Review and Analyses of Standard Review Plan Chapter 15 events for Palisades with a 15% Variable High Power Trip Reset." It is re_quested. that this change be made effective upon. issuance.
~
Gerald B*Slade General Manager CC: Administrator~ Region Ill, USNRC NRC Resident Inspector, Palisades Attachments
( 91061800Cl:3-9TOS3-C1 I
PDR AOOCK 05000255 P . . PDR A CMS' ENER5Y COMPANY
_!
,...,. ,
- a. Uncontrolled Control Bank Withdrawal at Power 14.2.2 MDNBR-1.420.
- b. Control Rod Mis-operation 14.2.3 MDNBR-1.197.
In both events the Minimum Departure from Nucleate Boiling Ratio (MDNBR) was greater than the Technical Specification Limit for Cycle 9 (1.190 for Kand L fuel, and 1.174 for M fuel) and only changed by -1.5% and -4.0% respectively from the previous analysis (ANF-90-078). The purpose of making this set point change is to eliminate unnecessary plant trips following a rapid power reduction from high power levels. Near beginning of cycle (BOC) conditions, the positive reactivity feedback due to a S/G overcooling event, can increase the core power more than 10% above the minimum power level as steady state conditions are reached.
By changing the VHPT from 10% to 15%, reactor trips could be avoided thereby, not putting the plant through unnecessary transients. The higher delta-power of 15% is still low enough to provide the minimum departure from nucleate boiling (MDNB) margins required for all other affected transients.
- 2. Create the possibility of a new or different kind of accident from any previously evaluated.
The proposed technical specification change does not create the.
possibility of a new or different kind of accident from any previously evaluated. The VHPT set point is used to define the radial peaking factors as a function of power that are used in the generation of the core protection limits for the thermal margin/low pressure (TM/LP). ANF-90-181 contains ANF's disposition of Chapter 15 analysis which identifies the events that. are impacted by the proposed increase. SRP events 15.4.2, and 15.4.3 are the only two events that were identified requiring reanalysis. The plant hardware was not changed and the plant operating conditions were not changed.
- 3. Involve a significant reduction in the margin of safety.
The margin of safety as defined by plant licensing bases is not s i gn'i f i cant l y reduced by the proposed technical spec if i cation change. The proposed technical specification maintains 95%
probability, at a 95% confidence level, that departure from nucleate boiling (DNB) will not occur for all reactivity insertion transient calculations. Plant safety also may be increased by reducing the potential for unnecessary plant trips.
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 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 in Section I below:
I. Changes A. In Table 2.3.1, "Reactor Protection System Trip Setting Limits," revise both the four and three primary coolant pumps operation "Variable High Power" set point from "~ 10% above core power," to "~ 15% above core power."
B. In 2.3, "Basis," Item 1, change the first full paragraph as indicated in Attachment 2. In the second full paragraph of the same section, change the footnote as indicated in Attachment 2.
Also change Reference 1 from "ANF-90-078, Table 15.0.7-1" to "ANF-90-181, Section 15.0.7." and change Reference 4 from "ANF-90-078, Section 15.0.7-1" to "ANF-90-078, Section 15.0.7".
II. Discussion Description of Item The variable high power trip'(VHPT) is incorporated in the reactor protection system (RPS) to provide a reactor trip for transients exhibiting a core power increase from any initial power level. The variable high power function is enabled at approximately 30% power with [
the current variable trip reset margin set at 10%. The proposed technical specification changes the variable trip reset margin to 15%.
III. Analysis of No Significant Hazards Consideration Consumers Power Company finds that activities associated with this proposed Technical Specifications change involve no significant hazards; and accordingly, a no significant hazards determination per 10CFR50.92(c) is justifted. The following evaluation supports the finding that the proposed changes would not:
- 1. Involve a significant increase in the possibility or consequences of an accident previously evafoated.
The proposed technical specification changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. Advanced Nuclear Fuels (ANF)-
90-181, "Review and Analysis of Standard Review Plan (SRP)
Chapter 15 Events for Palisades with a 15% Variable High Power Trip Reset", is the safety analysis that bounds the proposed technical specification change. Two events were re-analyzed for increasing the variable trip set point from 10% - 15%;
,
III. Conclusion The Palisades Plant Review.Committee has reviewed this Technical Specifications Change Request and*has determined'that *this* change
- does not involve.an unreviewed safety question. Further, the change involves no significant hazards consi~eration. This change
- has been .reviewed by the Nuclear Safety Services Department. A copy of this Technical Specifications 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 Specifications Change Request are truthful and complete.
- Sworn and' subscribed to* before* me this 4th day* of _*_J_u_n_e_ _ _ _ 1991.
[eANN MORSE, NOTARY PUBLIC
- VAN BUREN COUNTY, STATE OF MICHIGAN LeAnn Morse, Notary Public ' MY COMMISSION EXPIRES 06-06**94 .
Van Buren Co, Michigan
'My commission*expires~ June 6' 1994