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| {{#Wiki_filter:consumers Power company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-1636 October 25, 1984 Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -David J VandeWalle Director of Nuclear Licensing PALISADES PLANT -TECHNICAL SPECIFICATION CHANGE REQUESTS MODIFICATION RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS) By letter dated July 31, 1984, Consumers Power Company submitted our proposed Radiological Effluent Technical Specifications (RETS) for our Palisades Plant, and committed to their implementation on January 1, 1985. During procedure development for implementation of the RETS, Consumers Power Company has identified two areas where minor changes to our proposed RETS are required. | | {{#Wiki_filter:consumers Power David J VandeWalle company Director of Nuclear Licensing General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-1636 October 25, 1984 |
| A summary of these required changes is below. Waste Gas Release -Xenon-133 Proposed technical specification 3.24.6.1 states *** "the waste gas decay tank with the lowest Xe-133 concentration shall be released." This action ment was written in conformance with the wording of the model RETS (Reference 1). The gas decay tanks at the Palisades Plant are of two capacities. | | : Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - TECHNICAL SPECIFICATION CHANGE REQUESTS MODIFICATION RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS) |
| Release of waste gas in accordance with the above action statement could therefore result in a larger total amount of Xe-133 being released in the event that a larger capacity tank contains gas with a lower Xe-133 tion than a smaller capacity tank. In order to ensure that the intent of this specification is satisfied, Consumers Power Company is requesting this action statement be changed to " *.* the waste gas tank with the lowest Xe-133 content shall be released." Accident Monitoring Instrumentation | | By letter dated July 31, 1984, Consumers Power Company submitted our proposed Radiological Effluent Technical Specifications (RETS) for our Palisades Plant, and committed to their implementation on January 1, 1985. During procedure development for implementation of the RETS, Consumers Power Company has identified two areas where minor changes to our proposed RETS are required. A summary of these required changes is below. |
| -Location of Process Monitor Requirements Consumers Power Company determined that all process monitor requirements should be located within one table to facilitate plant operations (Reference 2). This resulted in the listing of three process monitors used during and after an accident in Table 3.24-2 of the proposed RETS. These three process monitors are the High Range Noble Gas Monitor, Main Steam Safety and Dump Valve Discharge Line Monitor and Engineered Safeguards Room Vent System Monitor. | | Waste Gas Release - Xenon-133 Proposed technical specification 3.24.6.1 states *** "the waste gas decay tank with the lowest Xe-133 concentration shall be released." This action state-ment was written in conformance with the wording of the model RETS (Reference 1). The gas decay tanks at the Palisades Plant are of two capacities. |
| ... ,Director, NRR Palisades Plant TSCR MODIFICATION
| | Release of waste gas in accordance with the above action statement could therefore result in a larger total amount of Xe-133 being released in the event that a larger capacity tank contains gas with a lower Xe-133 concentra-tion than a smaller capacity tank. In order to ensure that the intent of this specification is satisfied, Consumers Power Company is requesting this action statement be changed to " *.* the waste gas tank with the lowest Xe-133 content shall be released." |
| -RETS October 25, 1984 Proposed Specification 3.24.2.1 states that the instrumentation of Table 3. 24-2 shall have "their alarm/trip set points set to ensure that the l_imits of Specification 3.24.5.1 (essentially the MPC-maximum permissable tion) are not_exceeded." This Limiting Condition of Operation (LCO) is not appropriate for the above three process monitors as the setpoints for these instruments are governed by the Emergency Implementing Procedures per NUREG-0737 or other technical specifications. | | Accident Monitoring Instrumentation - Location of Process Monitor Requirements Consumers Power Company determined that all process monitor requirements should be located within one table to facilitate plant operations (Reference 2). This resulted in the listing of three process monitors used during and after an accident in Table 3.24-2 of the proposed RETS. These three process monitors are the High Range Noble Gas Monitor, Main Steam Safety and Dump Valve Discharge Line Monitor and Engineered Safeguards Room Vent System Monitor. |
| Consumers Power Company is requesting that a footnote be added to our proposed Table that exempts these three instrument from_ Specification 3.24.5.1. | | |
| Since these changes constitute a modification to our previous RETS submittal, we understand that the technical specification change request fees will be covered under our earlier submittal of July 31, 1984. Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident | | ,Director, NRR 2 Palisades Plant TSCR MODIFICATION - RETS October 25, 1984 Proposed Specification 3.24.2.1 states that the instrumentation of Table |
| -Palisades Attachments OC1084-0007A-NL02 2 | | : 3. 24-2 shall have "their alarm/trip set points set to ensure that the l_imits of Specification 3.24.5.1 (essentially the MPC-maximum permissable concen~ra tion) are not_exceeded." This Limiting Condition of Operation (LCO) is not appropriate for the above three process monitors as the setpoints for these instruments are governed by the Emergency Implementing Procedures per NUREG-0737 or other technical specifications. |
| Director, NRR Palisades Plant TSCR MODIFICATION | | Consumers Power Company is requesting that a footnote be added to our proposed Table 3.24~2 that exempts these three instrument setpoi~ts from_ Specification 3.24.5.1. |
| -RETS October 25, 1984 Reference 1 Reference 2 NRC letter dated October 31, 1983 transmitting Draft "7" of NUREG-0472, Revision 3, "Standard Radiological Effluent Technical Specifications for Water Reactors, September 1982" DJVandeWalle (CPCo) to DMCrutchfield (NRC) "Palisades Plant Radiological Effluent Technical Specifications (RETS), Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP)," dated July 31, 1984 OC1084-0007A-NL02 3 | | Since these changes constitute a modification to our previous RETS submittal, we understand that the technical specification change request fees will be covered under our earlier submittal of July 31, 1984. |
| CONSUMERS POWER COMPANY DOCKET.50-255 | | Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Insp~ctor - Palisades Attachments OC1084-0007A-NL02 |
| -LICENSE DPR-20 -PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below: I. CHANGE(s) | | |
| A. Change specification 3.24.6.1 proposed in Consumers Power Company letter dated July .31, 1984, Action 'a', to read .** "the waste gas decay tank with the lowest Xe-133 content shall be released." B. Add footnote to Table 3.24-2 in our.proposed Technical tions change request dated July 31, 1984 "Radioactive Gaseous Effluent Monitoring Instrumentation" applicable to items: 3d. High Range Noble Gas (RIA 2327) Sa. Gross Gamma Activity Monitor (RIA 2323 and 2324) 6a. Noble Gas Activity Monitor (RIA 1810 and 1811) The Footnote shall read: "Instruments exempted from Specification 3.24.5.1 setpoints. | | Director, NRR 3 Palisades Plant TSCR MODIFICATION - RETS October 25, 1984 Reference 1 NRC letter dated October 31, 1983 transmitting Draft "7" of NUREG-0472, Revision 3, "Standard Radiological Effluent Technical Specifications for P~essurized Water Reactors, September 1982" Reference 2 DJVandeWalle (CPCo) to DMCrutchfield (NRC) "Palisades Plant Radiological Effluent Technical Specifications (RETS), Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP)," dated July 31, 1984 OC1084-0007A-NL02 |
| Setpoints for these instruments are governed by Emergency Implementing Procedures,operating procedures or technical specifications." II. DISCUSSION A. This item being changed for the reasons specified in the cover lette.r to this change request. B. .This item being changed for the reasons specified in the cover letter to this change request. III. CONCLUSION The Palisades Plant Review Committee has*-reviewed this Technical cation Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no cant hazards consideration. | | |
| This change has also been reviewed under the cognizance of'the Nuclear Safety A copy of this Technical cation Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License. OC1084-0007B-NL02 | | CONSUMERS POWER COMPANY DOCKET.50-255 - LICENSE DPR PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below: |
| .... .:Director, NRR Palisades Plant TSCR MODIFICATION
| | I. CHANGE(s) |
| -RETS October 25, 1984 CONSUMERS POWER COMPANY By @b&1--1--1-rli-R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 25th day of October 1984. Sherry L Du ey, Notary Jackson Michigan My commission expires November 5, 1986. SHERRY l YNN DURFEY Notary Public, Jackson County, Mic1. My. Crrrrrission Nov. 5 1936 OC1084-0007B-NL02 2}} | | A. Change specification 3.24.6.1 proposed in Consumers Power Company letter dated July .31, 1984, Action 'a', to read .** "the waste gas decay tank with the lowest Xe-133 content shall be released." |
| | B. Add footnote to Table 3.24-2 in our.proposed Technical Specifica-tions change request dated July 31, 1984 "Radioactive Gaseous Effluent Monitoring Instrumentation" applicable to items: |
| | 3d. High Range Noble Gas (RIA 2327) Sa. Gross Gamma Activity Monitor (RIA 2323 and 2324) 6a. Noble Gas Activity Monitor (RIA 1810 and 1811) |
| | The Footnote shall read: "Instruments exempted from Specification 3.24.5.1 setpoints. Setpoints for these instruments are governed by Emergency Implementing Procedures,operating procedures or technical specifications." |
| | II. DISCUSSION A. This item being changed for the reasons specified in the cover lette.r to this change request. |
| | B. .This item being changed for the reasons specified in the cover letter to this change request. |
| | III. CONCLUSION The Palisades Plant Review Committee has*-reviewed this Technical Specifi-cation Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no signifi-cant hazards consideration. This change has also been reviewed under the cognizance of'the Nuclear Safety Boar~. A copy of this Technical Specifi-cation Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License. |
| | OC1084-0007B-NL02 |
| | |
| | .:Director, NRR 2 Palisades Plant TSCR MODIFICATION - RETS October 25, 1984 CONSUMERS POWER COMPANY By @b&1--1--1-rli-R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 25th day of October 1984. |
| | Sherry L Du ey, Notary Jackson ~ounty, Michigan My commission expires November 5, 1986. |
| | SHERRY l YNN DURFEY Notary Public, Jackson County, Mic1. |
| | My. Crrrrrission Exriir~~ Nov. 5 1936 OC1084-0007B-NL02}} |
|
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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 David J VandeWalle company Director of Nuclear Licensing General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-1636 October 25, 1984
- Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - TECHNICAL SPECIFICATION CHANGE REQUESTS MODIFICATION RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS)
By letter dated July 31, 1984, Consumers Power Company submitted our proposed Radiological Effluent Technical Specifications (RETS) for our Palisades Plant, and committed to their implementation on January 1, 1985. During procedure development for implementation of the RETS, Consumers Power Company has identified two areas where minor changes to our proposed RETS are required. A summary of these required changes is below.
Waste Gas Release - Xenon-133 Proposed technical specification 3.24.6.1 states *** "the waste gas decay tank with the lowest Xe-133 concentration shall be released." This action state-ment was written in conformance with the wording of the model RETS (Reference 1). The gas decay tanks at the Palisades Plant are of two capacities.
Release of waste gas in accordance with the above action statement could therefore result in a larger total amount of Xe-133 being released in the event that a larger capacity tank contains gas with a lower Xe-133 concentra-tion than a smaller capacity tank. In order to ensure that the intent of this specification is satisfied, Consumers Power Company is requesting this action statement be changed to " *.* the waste gas tank with the lowest Xe-133 content shall be released."
Accident Monitoring Instrumentation - Location of Process Monitor Requirements Consumers Power Company determined that all process monitor requirements should be located within one table to facilitate plant operations (Reference 2). This resulted in the listing of three process monitors used during and after an accident in Table 3.24-2 of the proposed RETS. These three process monitors are the High Range Noble Gas Monitor, Main Steam Safety and Dump Valve Discharge Line Monitor and Engineered Safeguards Room Vent System Monitor.
,Director, NRR 2 Palisades Plant TSCR MODIFICATION - RETS October 25, 1984 Proposed Specification 3.24.2.1 states that the instrumentation of Table
- 3. 24-2 shall have "their alarm/trip set points set to ensure that the l_imits of Specification 3.24.5.1 (essentially the MPC-maximum permissable concen~ra tion) are not_exceeded." This Limiting Condition of Operation (LCO) is not appropriate for the above three process monitors as the setpoints for these instruments are governed by the Emergency Implementing Procedures per NUREG-0737 or other technical specifications.
Consumers Power Company is requesting that a footnote be added to our proposed Table 3.24~2 that exempts these three instrument setpoi~ts from_ Specification 3.24.5.1.
Since these changes constitute a modification to our previous RETS submittal, we understand that the technical specification change request fees will be covered under our earlier submittal of July 31, 1984.
Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Insp~ctor - Palisades Attachments OC1084-0007A-NL02
Director, NRR 3 Palisades Plant TSCR MODIFICATION - RETS October 25, 1984 Reference 1 NRC letter dated October 31, 1983 transmitting Draft "7" of NUREG-0472, Revision 3, "Standard Radiological Effluent Technical Specifications for P~essurized Water Reactors, September 1982" Reference 2 DJVandeWalle (CPCo) to DMCrutchfield (NRC) "Palisades Plant Radiological Effluent Technical Specifications (RETS), Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP)," dated July 31, 1984 OC1084-0007A-NL02
CONSUMERS POWER COMPANY DOCKET.50-255 - LICENSE DPR PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below:
I. CHANGE(s)
A. Change specification 3.24.6.1 proposed in Consumers Power Company letter dated July .31, 1984, Action 'a', to read .** "the waste gas decay tank with the lowest Xe-133 content shall be released."
B. Add footnote to Table 3.24-2 in our.proposed Technical Specifica-tions change request dated July 31, 1984 "Radioactive Gaseous Effluent Monitoring Instrumentation" applicable to items:
3d. High Range Noble Gas (RIA 2327) Sa. Gross Gamma Activity Monitor (RIA 2323 and 2324) 6a. Noble Gas Activity Monitor (RIA 1810 and 1811)
The Footnote shall read: "Instruments exempted from Specification 3.24.5.1 setpoints. Setpoints for these instruments are governed by Emergency Implementing Procedures,operating procedures or technical specifications."
II. DISCUSSION A. This item being changed for the reasons specified in the cover lette.r to this change request.
B. .This item being changed for the reasons specified in the cover letter to this change request.
III. CONCLUSION The Palisades Plant Review Committee has*-reviewed this Technical Specifi-cation Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no signifi-cant hazards consideration. This change has also been reviewed under the cognizance of'the Nuclear Safety Boar~. A copy of this Technical Specifi-cation Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.
OC1084-0007B-NL02
.:Director, NRR 2 Palisades Plant TSCR MODIFICATION - RETS October 25, 1984 CONSUMERS POWER COMPANY By @b&1--1--1-rli-R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 25th day of October 1984.
Sherry L Du ey, Notary Jackson ~ounty, Michigan My commission expires November 5, 1986.
SHERRY l YNN DURFEY Notary Public, Jackson County, Mic1.
My. Crrrrrission Exriir~~ Nov. 5 1936 OC1084-0007B-NL02