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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
[Table view] |
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'\ consumers Power POW ERi Nii MICHlliAN'S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 April 15, 1992 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 GB Slade General Manager DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -TECHNICAL SPECIFICATIONS CHANGE REQUEST -OVERPRESSURE PROTECTION Enclosed is a request for a change to the Palisades Technical Specifications to incorporate GL 90-06 Power Operated Relief Valve (PORV) requirements for power operation, and to modify the Primary Coolant System (PCS) overpressure protection specification venting requirements.
The proposed specification for PORV operability during power operation, 3.1.8.1, implements the applicable model Technical Specifications attached to GL 90-06. This part of the change request completes our response to GL 90-06 in accordance with our letter of December 26, 1990. The proposed PCS venting changes are the result of analyses conducted in conjunction with the installation of the new PORVs and block valves in 1989. It replaces the 1.3 square inch vent size requirements with vent flow capacity requirements, restructures the Action statements and modifies the Basis of the specification.
Attachment 1 to the change request contains the proposed Technical Specifications pages; Attachment 2, marked up pages of the existing Technical Specifications showing the proposed changes. In order to allow the necessary procedure revisions and operator training to be accomplished, it is requested that this change request be made effective 60 days after approval. Gerald B Slade General Manager CC Administrator, Region III, USNRC Resident Inspector, Palisades Attachments rJ*00 1 n .I I. ' . ._;_ '-
PDR PDR I *I. I . ,I I *r "\ . /) A'CMS' ENER<SY COMPANY p -
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 below: I. Changes A. Technical Specification 3.1.8 is changed as follows: 1. A new Specification 3.1.8.1, PORV requirements when the plant is at Hot Standby and above, has been added to implement the model Technical Specification of GL 90-06. 2. Existing Specification 3.1.8.1, PORV requirements when below 430°F, has been renumbered as 3.1.8.2, and revised to: a. Coordinate the Action statements with those of the proposed 3.1.8.1. . 1 b. Specify a minimum vent flow capacity instead of the existing specification of a minimum flow area. c. Delete the exception to the provisions of 3.0.3 and add an exception to 4.0.4. d. Simplify and clarify the wording. This change request proposes use of a stipulated vent flow capability rather than a stipulated vent area to avoid possible misinterpretation of the specification.
a flow area of 1.3 square inches would be provided by two parallel paths each having an area of 0.65 square inches, or by a single vent of 1.3
- square inches on the.end of a long run of pipe. Neither of these examples would necessarily provide the intended relief capacity.
- 3. The Basis section for Specification 3.1.8 has been revised to discuss the newly added requirements.
B. Table 3.17.4, Item 11, "PORV Isolation Valve Position Indication" is revised to refer to specification 3.1.8, rather than to repeat the venting criterion and to use the term "Block Valve", rather than "Isolation Valve.". C. Surveillance Requirement 4.1.1 has been revised to include additional testing in accordance with GL 90-06.
n ' 2 II. Discussion A. The proposed Palisades PORV specifications differ from the model Technical Specifications in form and in content. Palisades does not utilize Standard Technical Specifications, therefore, the format of the proposed specifications differs from those provided in GL 90-06. Palisades safety analyses do not assume automatic PORV operation above a temperature of 430°F, but do assume automatic, variable setpoint operation when below 430°F. Existing specifications address PORV operability below 430°F. Two specifications are proposed; one applicable at Hot Standby and above, and one below 430°F. Proposed specification 3.1.8.1, applicable at Hot Standby and above, stipulates requirements similar to those of GL 90-06 specification
3.4.4. Proposed
specification 3.1.8.2 maintains the requirements of existing Palisades specification 3.1.8.1. 1. The proposed specification 3.1.8.1 differs from GL 90-06 specification 3.4.4 for the following reasons: a. The wording of proposed specification 3.1.8.1 differs from that of GL 90-06 specification 3.4.4 in order address the required function of two operable flow paths, rather than to simply address the required components.
- b. Action "a" of GL 90-06 was omitted from the proposed specification for two reasons. First, 'there is neither a reference to a seat leakage limit in the GL 90-06 LCO nor in the GL 90-06 surveillance requirements, so it would not be possible to determine how much leakage would make the valve inoperable.
Second, Palisades Technical Specifications already contain limitations on PCS leakage and Actions to be taken if those limitations are exceeded.
Adding an Action for PCS leakage in the PORV specification would, therefore, be redundant.
- c. Actions "b" and "d" of GL 90-06 were combined for a single inoperable valve, Actions "c" and "d" of GL 90-06 were combined for two inoperable valves, to better address the PORV function, rather only the individual components.
The proposed Action statements address one PORV and the opposite block valve being inoperable, which those of GL 90-06 did not. d. The proposed Actions do not force the plant into a mode where the PORVs are required for pressure control. Instead, the proposed Actions require a shutdown, but not a cooldown.
The intent is to allow repairs to be made without entering conditions where the valves are required for LTOP, when possible, or to allow planning of a controlled cooldown when the valves cannot be repaired while the PCS is above 430°F.
,. ' e.
- All completion times are referenced to discovery that the Action statement applies. The completion time proposed for reaching Hot Shutdown is the same as that currently specified in the Palisades specifications for the Reactor Protective System and other equipment.
Note that Palisades "HOT SHUTDOWN" definition is similar to the Standard Technical Specifications "HOT STANDBY" definition.
- f. The 3.0.4 exception is limited to specification 3.1.8.2, thus prohibiting a startup with an inoperable PORV or block valve. g. The removal of power from a block valve which has been closed to isolate an inoperable PORV was not required because the time in this condition is limited to 72 Most PORV inoperabilities are administrative involving no actual loss of function, or involving failures which result in the PORV being failed closed, rather than resulting in a potential for spurious opening. In addition, a failure which would cause a closed block valve to drive open is unlikely, and for such a failure to occur concurrently.with a failure of the associated PORV, within a given 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period is even more remote. The proposed Action maintains pressure control capability when the PORV is still functional but allows power removal if it is deemed necessary.
- 2. The change, in specification 3.1.8.2, from specifying a particular vent area to specifying a vent path flow capability more clearly aligns the requirements of the specification the assumptions of the analyses.
The need for a occurred because it was discovered that newly installed PCS manual vent valves, which had been understood to have an effective area of 1.33 square inches, actually had an effective area of 1.228 square inches, slightly smaller than the specified vent area of square inches. 3 Analysis showed that the newly installed manual vent valve area was sufficient to meet Appendix G criterion.
However, since the valves did not meet the area requirement of the Technical Specification, they have not been relied upon to meet the venting requirements of LCO 3.1.8 or of Table 3.17.4. The basis for the 1.3 square inch vent area requirement is not clear. It is believed, however, that it was the choking area of one of the original Dresser PORVs. The intent of the requirement is to protect the primary coolant system (PCS) from pressure transients which could exceed the 10 CFR 50, Appendix G, limits with the PORVs inoperable.
No analysis has been found that showed a 1.3 square inch vent area would protect the PCS from exceeding the Appendix G curve limit.
4 Analysis concluded that manual vent valves and PC-515 will provide a relief capacity of 167 gpm at a PCS pressure of =115 psig, well below the minimum 331 psig limit (Appendix G curve limit for a 40°F/hr heat-up).
This relief capacity will protect the PCS against a pressure transient caused by a maximum charging/letdown imbalance coincident with a 40°F/hr PCS heat-up rate and a 60°F/hr pressurizer heat-up rate. Two other pressure transients, a high pressure safety injection (HPSI) pump start and a primary coolant pump (PCP) start, discussed in the proposed Technical Specification 3.1.8 Basis, are also precluded.
With the PCS in a and depressurized state, the PCS would be below 212°F. Technical Specification 3.3.2g requires both HPSI pumps to be rendered inoperable below 260°F and, with the system depressurized, normal operating procedures prohibit a primary coolant pump start due to insufficient pump net positive suction head (NPSH). Additional analysis confirmed that the SDC relief capacity, prior to the installation of PC-514 and PC-515, was adequate to provide overpressure protection of the SDC system for the pressure transient evaluated for PC-514 and PC-515. Therefore, the 1.3 square inch requirement can be replaced with a requirement to have a vent capable of relieving 167 gpm at a PCS pressure less than or equal to 300 psig. The 300 psig limit was chosen to allow for future Appendix G limits below the present limit. The Appendix G limits are revised periodically to account for the continuing effects of irradiation on the PCS. The basis for Technical Specification 3.1.8 is updated to provide the limitations that apply to the new requirements which ensure an overpressurization of the PCS does not occur. B. Table 3.17.4, item 11, PORV block valve position indication, has been changed to utilize the term "block valve" rather than "isolation Valve" for consistency with specification 3.1.8 and with general plant usage. The associated Permissible Bypass Condition entry has been changed to reference specification 3.1.8, rather than to repeat the specific PCS vent requirement.
C. Surveillance Requirement 4.1.1 has been revised to include requirements to cycle each PORV and each block valve each 18 months. The block valve surveillance frequency of "once per 92 days" suggested in GL 90-06 is inappropriate for Palisades.
Palisades does not assume automatic PORV operation, other than for LTOP, in any safety analyses, and operates with the block valves closed when above the LTOP range. Opening the block valves during power operation may cause the PORVs to momentarily relieve, with a subsequent increased chance of seat leakage. A frequency of "18 Months" is proposed.
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III. Analysis of No Significant Hazards Consideration Consumers Power Company finds the activities associated with this proposed Technical Specifications change involve no significant hazards and accordingly, a no significant hazards determination per 10CFR50.92(c) is justified.
The following evaluation supports the finding that operation of the facility in accordance with the proposed change would not: 1. Involve a significant increase in the probability or consequences of an accident previously evaluated.
5 The proposed Technical Specification requiring Operability of the PORVs and their block valves does not alter plant operation or configuration in any way. It is current practice to maintain these valves in an Operable condition to meet the requirements of existing Specification 3.1.8, which is applicable when below 430°F. The effect of the proposed changes is to extend the applicability of the Operability requirement for these valves. The addition of PORV Operability requirements when at Hot Standby and above would not involve a significant increase in the probability or consequences of an accident previously evaluated.
Replacing the requirements to vent the PCS through a 1.3 square inch vent with a vent capable of relieving 167 gpm at a pressure less than the Appendix G limits will not significantly increase the probability or consequences of an overpressurization event occurring.
The 1.3 square inch vent area in Technical Specification 3.1.8 was intended to be a means of protecting the Primary Coolant System (PCS)' from exceeding the limit of the 10 CFR 50, Appendix G, curve following an overpressure transient.
Analysis has shown that manual vent valves PC-514 and PC-515.will provide a relief capacity of 167 gpm at a PCS pressure of =115 psig, well below the minimum 331 psig limit (Appendix G curve limit for a 40°F/hr heat-up).
This relief capacity will protect the PCS against a pressure transient caused by a maximum charging/letdown imbalance coincident with a 40°F/hr PCS heat-up rate and a 60°F/hr pressurizer heat-up rate. Two other pressure transients, a.High Pressure Safety Injection (HPSI) pump start and a Primary Coolant Pump (PCP) start, are also precluded.
With the PCS in a vented and depressurized state, the PCS would be below 212°F. Existing technical specifications require both HPSI pumps to be rendered inoperable below 260°F and, with the system depressurized, normal operating procedures prohibit a PCP start due to insufficient pump net positive suction head (NPSH). Therefore, the 1.3 square inch requirement can be replaced with a requirement to have a vent capable of relieving 167 gpm at a PCS pressure .less than or equal to the Appendix G limit with no significant increase in the probability or consequences of an overpressurization event occurring.
6 2. Create the possibility of a new or different kind of accident from any previously evaluated.
The addition of PORV Operability requirements when at Hot Standby and above will not alter plant operation or configuration.
It will not alter any equipment or analyses.
Therefore the addition of these PORV operability requirements will not create the possibility of a new or different kind of accident from any previously evaluated.
The new technical specifications requirements for PCS vent capacity will provide an equivalent or better, overpressure protection as compared to the existing requirement.
No analysis has been found that shows that the existing 1.3 square inch vent area will protect the PCS from exceeding the Appendix G curve limit. However, analysis has been developed which shows that manual vent valves PC-514 and PC-515 will provide adequate relief capacity, maintaining PCS pressure within* the 10 CFR 50, Appendix G, limits. Furthermore, two other pressure transients, a HPSI pump start and a PCP start, are also precluded by either existing technical specifications or normal plant operating procedures.
Another related analysis has shown that relief valve RV-3164, the Low Pressure Safety Injection (LPSI) pumps, the LPSI pump seals, and the system piping of the shutdown cooling system have the capability of providing adequate overpressure protection to the shutdown cooling system. The addition of the manual vent valves do not introduce a vent path where a vent path had not previously existed. Therefore, the possibility of an accident of a new or different type, than previously evaluated in the FSAR, will not be created. 3. Involve a significant reduction in a margin of safety. The margin of safety will not be reduced by the proposed Technical_
The of PORV Operability requirements has no effect on any margin of safety. The previous requirement assumed that a vent with an equivalent flow area as the original PORV would provide the same relief as the PORV itself and gave no consideration to how that flow area should factor in system losses or vent location.
The new technical specification requirement offers a means to ensure the PCS will be protected against all achievable overpressure transients for the system configuration, with analyses to support it.
- 7 IV. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specifications Change Request and has determined that proposing this change does not involve an unreviewed safety question.
Further, the change involves no significant hazards consideration.
This change has been reviewed by the Nuclear Performance Assessment Department.
A copy of this Technical Specifications Change Request has been sent to the State of Michigan 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.
David P Hoffman, Vi Nuclear Operations Sworn and subscribed to before me this jJ day of 1992. Lo. Ow,__ 0m &fU,L Notary Public , Michigan My commission expires *.C:eANN MORSEi NOT,ARY PUBLIC' YA!'! BU.REN COUNTY, STATE OF MICHIGAN MY: .COMMISSION EXPIRES
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