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| | issue date = 03/18/1992 | | | issue date = 03/18/1992 |
| | title = Application for Amend to License DPR-20,revising TS Re Shutdown Cooling | | | title = Application for Amend to License DPR-20,revising TS Re Shutdown Cooling |
| | author name = SLADE G B | | | author name = Slade G |
| | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), | | | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), |
| | addressee name = | | | addressee name = |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 3 | | | page count = 3 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| {{#Wiki_filter:consumers Power POW ERi Nii MICHlliAN"S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 March 18, 1992 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 LICENSE DPR-20 -PALISADES PLANT -GB Slade General Manager SHUTDOWN COOLING TECHNICAL SPECIFICATIONS CHANGE REQUEST REPLACEMENT PAGES Enclosed please find the Palisades proposed Shutdown Cooling (SOC) Technical Specifications pages altered to include those changes which were discussed with the NRC Palisades Project Manager by our licensing staff. Enclosure 1 includes revised pages as they should appear in the Technical Specifications, and revised bases pages. The revised pages have been rewritten to enhance their clarity and brevity, and reformatted to conform with other Technical Specifications change requests (TSCRs) which have been submitted after the earlier Shutdown Cooling TSCR. lhe revised pages, 3-25d through 3-25i should replace pages 3-25e through 3-25i proposed in our September 26, 1991 submittal. | | {{#Wiki_filter:consumers Power GB Slade General Manager POWERiNii MICHlliAN"S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 March 18, 1992 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 ~ LICENSE DPR PALISADES PLANT - |
| The altered page numbering eliminates an unused page. The revised pages contain the below listed changes to the requirements of the pages of our September 26, 1991 submittal. | | SHUTDOWN COOLING TECHNICAL SPECIFICATIONS CHANGE REQUEST REPLACEMENT PAGES Enclosed please find the Palisades proposed Shutdown Cooling (SOC) Technical Specifications pages altered to include those changes which were discussed with the NRC Palisades Project Manager by our licensing staff. Enclosure 1 includes revised pages as they should appear in the Technical Specifications, and revised bases pages. |
| These changes are indented to make the proposed specifications more closely match the CE Standard Technical Specifications (STS), yet allow required and necessary maintenance to be performed. | | The revised pages have been rewritten to enhance their clarity and brevity, and reformatted to conform with other Technical Specifications change requests (TSCRs) which have been submitted after the earlier Shutdown Cooling TSCR. |
| lhe STS requirements were not wr1tten for a plant with the Palisades system configuration. | | lhe revised pages, 3-25d through 3-25i should replace pages 3-25e through 3-25i proposed in our September 26, 1991 submittal. The altered page numbering eliminates an unused page. |
| If it would aid the staff reviewers, members of the Palisades staff could present an explanation of the plant features which require differences between our Technical Specifications and the STS. 1) An additional required action is included for the case when the PCS is between 200°F and 300°F, with fewer operable means of decay heat removal required: (former item 3.l.9a Action 2; revised 3.1.9.1 Action l.b) "Maintain PCS temperature as low as practical with available equipment." This Required Action is intended to make the proposed Actions meet the intent of the. STS LCO 3.4.1.3 Actions, that if there is actually no functional (vs technically OPERABLE) | | The revised pages contain the below listed changes to the requirements of the pages of our September 26, 1991 submittal. These changes are indented to make the proposed specifications more closely match the CE Standard Technical Specifications (STS), yet allow required testin~ and necessary maintenance to be performed. lhe STS requirements were not wr1tten for a plant with the Palisades system configuration. If it would aid the staff reviewers, members of the Palisades staff could present an explanation of the plant features which require differences between our Technical Specifications and the STS. |
| SOC train, that a cooldown to Cold Shutdown not be possible. | | : 1) An additional required action is included for the case when the PCS is between 200°F and 300°F, with fewer operable means of decay heat removal required: (former item 3.l.9a Action 2; revised 3.1.9.1 Action l.b) |
| Also note that limitations on starting a Pr1mary Coolant Pump, given at the bottom of STS page 3/4 4-3, already appear in Palisades LCO 3.1.lh. 9203250164 920318 PDR ADOCK 05000255 I I I_) A CMS' ENERGY COMPANY P _,_;. *.** PDR .... -- | | "Maintain PCS temperature as low as practical with available equipment." |
| : 2) The SDC requirements with the below 200°F with the lobps filled has been rewritten to closely follow STS LCO 3.4.1.4. :j This change limits the use of the PCS as a backup means of decay heat removal (with the PCS and loops filled) to those times when both PCS loops and both steam generators are available for heat removal. 3) An additional constraint has been added to the exceptions which allow temporary stoppage of flow through the reactor core when the PCS is below 200°F: "Two SDC loops are OPERABLE." This added constraint is intended to reduce the risk of not being able to restart SDC following intentional flow stoppage.
| | This Required Action is intended to make the proposed Actions meet the intent of the. STS LCO 3.4.1.3 Actions, but~reco9nize that if there is actually no functional (vs technically OPERABLE) SOC train, that a cooldown to Cold Shutdown mi~ht not be possible. Also note that limitations on starting a Pr1mary Coolant Pump, given at the bottom of STS page 3/4 4-3, already appear in Palisades LCO 3.1.lh. |
| : 4) The exception allowing one SDC train to be intentionally rendered inoperable for testing or maintenance, with the PCS less than 200°F and the loops not filled, has been rewritten; a similar exception has been proposed for when the PCS is less than 200°F with the loops filled. PCS loops filled: "Both SDC loops may be intentionally rendered inoperable for maintenance provided: | | 9203250164 920318 I I |
| : a. One PCS or SDC loop is providing flow through the reactor core, and b. Core outlet temperature stays and c. Each steam generator secondary water level is PCS loops not filled: "Both SDC loops may be intentionally rendered inoperable | | PDR ADOCK 05000255 P.... _,_;. |
| *for provided: | | ~ - - *.** PDR I_) A CMS' ENERGY COMPANY |
| : a. One PCS or SDC loop is providing flow through the reactor core, and b. Core outlet temperature stays and c. refueling cavity water level is This exception is intended to allow maintenance on the systems which support SDC as long as circulation is maintained through the reactor core, an operable means of decay heat removal is available, and PCS temperature is maintained within limits. An additional restriction is provided by LCO 3.1.2, which limits the allowable PCS heatup rate. The exemption requires either both PCS loops or the refueling cavity, containing sufficient cooling water to act as a heat sink, to be available. | | |
| The heat sink available at the proposed level of (22' 6" above the reactor vessel flange) has been analyzed. | | 2) |
| Curves predicting the time to reach 200°F, as a function of time after shutdown and initial temperature, are provided in Palisades operating procedures. | | ~ |
| | The specificati~for SDC requirements with the ~ below 200°F with the lobps filled has been rewritten to closely follow STS LCO 3.4.1.4. |
| | :j This change limits the use of the PCS as a backup means of decay heat removal (with the PCS ~200°F and loops filled) to those times when both PCS loops and both steam generators are available for heat removal. |
| | : 3) An additional constraint has been added to the exceptions which allow temporary stoppage of flow through the reactor core when the PCS is below 200°F: |
| | "Two SDC loops are OPERABLE." |
| | This added constraint is intended to reduce the risk of not being able to restart SDC following intentional flow stoppage. |
| | : 4) The exception allowing one SDC train to be intentionally rendered inoperable for testing or maintenance, with the PCS less than 200°F and the loops not filled, has been rewritten; a similar exception has been proposed for when the PCS is less than 200°F with the loops filled. |
| | PCS ~200°F, loops filled: |
| | "Both SDC loops may be intentionally rendered inoperable for maintenance provided: |
| | : a. One PCS or SDC loop is providing flow through the reactor core, and |
| | : b. Core outlet temperature stays ~200°F, and |
| | : c. Each steam generator secondary water level is ~-84%. |
| | PCS ~200°F, loops not filled: |
| | "Both SDC loops may be intentionally rendered inoperable *for mainte~ance provided: |
| | : a. One PCS or SDC loop is providing flow through the reactor core, and |
| | : b. Core outlet temperature stays ~200°F, and |
| | : c. ~he refueling cavity water level is ~647'. |
| | This exception is intended to allow maintenance on the systems which support SDC as long as circulation is maintained through the reactor core, an operable means of decay heat removal is available, and PCS temperature is maintained within limits. An additional restriction is provided by LCO 3.1.2, which limits the allowable PCS heatup rate. The exemption requires either both PCS loops or the refueling cavity, containing sufficient cooling water to act as a heat sink, to be available. The heat sink available at the proposed level of ~647' (22' 6" above the reactor vessel flange) has been analyzed. Curves predicting the time to reach 200°F, as a function of time after shutdown and initial temperature, are provided in Palisades operating procedures. |
| The referenced 647' level is the same minimum level used in refueling procedures. | | The referenced 647' level is the same minimum level used in refueling procedures. |
| This exception not appear in STS. Such an is necessary for the Palisades due to the configuration of our Component Cooling Water (CCW) and Service Water (SWS) systems. Palisades was licensed prior to publication of the General Design Criterion of 10 CFR 50, Appendix A. While the CCW and SWS systems designs do provide electrical redundancy and separation, they do not have the mechanical separation which is typical of the newer plants for which the STS were developed. | | |
| In each system there are components which require temporarily making the system inoperable to accomplish maintenance. | | This exception ~s not appear in STS. Such an ~eption is necessary for the Palisades due to the configuration of our Component Cooling Water (CCW) and Service Water (SWS) systems. Palisades was licensed prior to publication of the General Design Criterion of 10 CFR 50, Appendix A. |
| The duration of the exception is limited by the requirement to maintain the PCS temperature below 200°F. The exception is proposed for both the "loops filled" and the "loops not filled" cases to allow for maintenance of CCW or SWS in outages which do not involve refueling, as well as when the refueling cavity is available as a heat sink. | | While the CCW and SWS systems designs do provide electrical redundancy and separation, they do not have the mechanical separation which is typical of the newer plants for which the STS were developed. In each system there are components which require temporarily making the system inoperable to accomplish maintenance. The duration of the exception is limited by the requirement to maintain the PCS temperature below 200°F. |
| new restrictions on Shutdown Cooling operations will be implemented by administrative control. However, in order to allow operator training on these new requirements and to avoid confusion due to changing requirements during an outage, implementation will be delayed until after completion of the current refueling outage. The incorporation of these changes does not alter the conclusions of the Analysis of No Significant Hazards Consideration included in the September 26, 1991 submittal. Gerald B Slade General Manager CC Administrator, Region Ill, USNRC NRC Resident Inspector | | The exception is proposed for both the "loops filled" and the "loops not filled" cases to allow for maintenance of CCW or SWS in outages which do not involve refueling, as well as when the refueling cavity is available as a heat sink. |
| -Palisades Attachment}} | | Thes~ new restrictions on Shutdown Cooling operations will be implemented by administrative control. However, in order to allow operator training on these new requirements and to avoid confusion due to changing requirements during an outage, implementation will be delayed until after completion of the current refueling outage. |
| | The incorporation of these changes does not alter the conclusions of the Analysis of No Significant Hazards Consideration included in the September 26, 1991 submittal. |
| | ~ |
| | Gerald B Slade General Manager CC Administrator, Region Ill, USNRC NRC Resident Inspector - Palisades Attachment}} |
|
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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 MICHlliAN"S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 March 18, 1992 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 ~ LICENSE DPR PALISADES PLANT -
SHUTDOWN COOLING TECHNICAL SPECIFICATIONS CHANGE REQUEST REPLACEMENT PAGES Enclosed please find the Palisades proposed Shutdown Cooling (SOC) Technical Specifications pages altered to include those changes which were discussed with the NRC Palisades Project Manager by our licensing staff. Enclosure 1 includes revised pages as they should appear in the Technical Specifications, and revised bases pages.
The revised pages have been rewritten to enhance their clarity and brevity, and reformatted to conform with other Technical Specifications change requests (TSCRs) which have been submitted after the earlier Shutdown Cooling TSCR.
lhe revised pages, 3-25d through 3-25i should replace pages 3-25e through 3-25i proposed in our September 26, 1991 submittal. The altered page numbering eliminates an unused page.
The revised pages contain the below listed changes to the requirements of the pages of our September 26, 1991 submittal. These changes are indented to make the proposed specifications more closely match the CE Standard Technical Specifications (STS), yet allow required testin~ and necessary maintenance to be performed. lhe STS requirements were not wr1tten for a plant with the Palisades system configuration. If it would aid the staff reviewers, members of the Palisades staff could present an explanation of the plant features which require differences between our Technical Specifications and the STS.
- 1) An additional required action is included for the case when the PCS is between 200°F and 300°F, with fewer operable means of decay heat removal required: (former item 3.l.9a Action 2; revised 3.1.9.1 Action l.b)
"Maintain PCS temperature as low as practical with available equipment."
This Required Action is intended to make the proposed Actions meet the intent of the. STS LCO 3.4.1.3 Actions, but~reco9nize that if there is actually no functional (vs technically OPERABLE) SOC train, that a cooldown to Cold Shutdown mi~ht not be possible. Also note that limitations on starting a Pr1mary Coolant Pump, given at the bottom of STS page 3/4 4-3, already appear in Palisades LCO 3.1.lh.
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The specificati~for SDC requirements with the ~ below 200°F with the lobps filled has been rewritten to closely follow STS LCO 3.4.1.4.
- j This change limits the use of the PCS as a backup means of decay heat removal (with the PCS ~200°F and loops filled) to those times when both PCS loops and both steam generators are available for heat removal.
- 3) An additional constraint has been added to the exceptions which allow temporary stoppage of flow through the reactor core when the PCS is below 200°F:
"Two SDC loops are OPERABLE."
This added constraint is intended to reduce the risk of not being able to restart SDC following intentional flow stoppage.
- 4) The exception allowing one SDC train to be intentionally rendered inoperable for testing or maintenance, with the PCS less than 200°F and the loops not filled, has been rewritten; a similar exception has been proposed for when the PCS is less than 200°F with the loops filled.
PCS ~200°F, loops filled:
"Both SDC loops may be intentionally rendered inoperable for maintenance provided:
- a. One PCS or SDC loop is providing flow through the reactor core, and
- b. Core outlet temperature stays ~200°F, and
- c. Each steam generator secondary water level is ~-84%.
PCS ~200°F, loops not filled:
"Both SDC loops may be intentionally rendered inoperable *for mainte~ance provided:
- a. One PCS or SDC loop is providing flow through the reactor core, and
- b. Core outlet temperature stays ~200°F, and
- c. ~he refueling cavity water level is ~647'.
This exception is intended to allow maintenance on the systems which support SDC as long as circulation is maintained through the reactor core, an operable means of decay heat removal is available, and PCS temperature is maintained within limits. An additional restriction is provided by LCO 3.1.2, which limits the allowable PCS heatup rate. The exemption requires either both PCS loops or the refueling cavity, containing sufficient cooling water to act as a heat sink, to be available. The heat sink available at the proposed level of ~647' (22' 6" above the reactor vessel flange) has been analyzed. Curves predicting the time to reach 200°F, as a function of time after shutdown and initial temperature, are provided in Palisades operating procedures.
The referenced 647' level is the same minimum level used in refueling procedures.
This exception ~s not appear in STS. Such an ~eption is necessary for the Palisades due to the configuration of our Component Cooling Water (CCW) and Service Water (SWS) systems. Palisades was licensed prior to publication of the General Design Criterion of 10 CFR 50, Appendix A.
While the CCW and SWS systems designs do provide electrical redundancy and separation, they do not have the mechanical separation which is typical of the newer plants for which the STS were developed. In each system there are components which require temporarily making the system inoperable to accomplish maintenance. The duration of the exception is limited by the requirement to maintain the PCS temperature below 200°F.
The exception is proposed for both the "loops filled" and the "loops not filled" cases to allow for maintenance of CCW or SWS in outages which do not involve refueling, as well as when the refueling cavity is available as a heat sink.
Thes~ new restrictions on Shutdown Cooling operations will be implemented by administrative control. However, in order to allow operator training on these new requirements and to avoid confusion due to changing requirements during an outage, implementation will be delayed until after completion of the current refueling outage.
The incorporation of these changes does not alter the conclusions of the Analysis of No Significant Hazards Consideration included in the September 26, 1991 submittal.
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Gerald B Slade General Manager CC Administrator, Region Ill, USNRC NRC Resident Inspector - Palisades Attachment