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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 Kenneth W Berry POWERINli Director ll/llCHlliAN'S PROliRESS Nuclear licensing General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-1636 December 22, 1987 Nuclear Regulatory Connnission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR-20 -*PALISADES PLANT -
TECHNICAL SPECIFICATION CHANGE REQUEST - LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP)
The attached proposed change to the Palisades Technical Specifications is necessary to update the Low Temperature Overpressure Protection (LTOP) requirements. As the reactor vessel is exposed to fast neutrons, the ability of the material at the reactor heltline to resist brittle fracture at low temperatures is decreased. Periodically, the upper pressure limit at given temperatures must be lowered to keep the pressure/temperature relationship within the ductile range of the beltline material .
..
- Specifically, this proposed Technical Specification Change lowers the relief valve setting over the temperature range presently addressed in the Technical Specifications, provides LTOP protection up to the temperature where the pressurizer safety valves provide protection* against brittle fracture, and adds precautionary measures during heatup and cooldown.
- ,,: ~.. The proposed changes to the Technical Specifications are more restrictive than existing Technical Specifications. Consumers Power Company commits to operate
- the Palisades Plant in accordance with the proposed changes to the Technical Specifications until they are approved as a license amendment.
. -- l A check, for $150.00 as r~quired by* 10CFR170.21 is included.
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Kenneth W Berry Director, Nuclear Licensing CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment OC1287-0234-NL04
(
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 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. Changes A. Revise section 3.1.lh to read:
"h. During initial primary coolant pump starts (i.e., initiation of forced circulation), secondary system temp~rature in the steam generators shall be < the PCS cold leg temperature unless the PCS cold leg temperature is > 450°F."
B. Revise the last sentence of the last paragraph in the Basis for section 3.1 to read:
"The requirement that the steam generator temperature be < the PCS temperature when forced circulation is initiated ensures that an energy addition caused by heat transferred from the secondary system to the PCS will not occur. This requirement applies only to the initiation of forced circulation (the start of the first primary coolant pump) when the PCS cold leg temperature us < 450°F. At or above 450°F, the PCS safety valves prevent the PCS pressure from exceeding 10CFRSO Appendix G limits .n C. Section 3.l.2a has been revised to restrict heatup rate limitations at low temperatures.
D. Proposed Section 3.l.2b has been revised to restrict cooldown rates at low temperatures.
E. Section 3.l.2c has been revised to include the heatup and cooldown rate restrictions as proposed in Section 3.l.2a and b.
F. Section 3.l.2d has been revised to restrict the pressurizer heatup rate. ,
G. Revise the last sentence of the first partagraph in Basis for Section 3.1.2 to read:
"A plant heatup and cooldown limit of 100°F per hour is consistent with the design ny,~er of cycles and satisfies stress limits for cyclic operation. "
OC1287-0234-NL04
2 H. The following two paragraphs have been proposed at the end of the Basis for Section 3.1.2.
II 1 The restriction of average heatup and cooldown rates to 100°F/h when all PCS cold legs are ~ 450°F and the maintenance of a pressure~.temperature relationship under the heatup, cooldown and inservice test curves of Figures 3-1, 3-2 and 3-3, respectively, ensures that the requirements of References 6, 7, 8 and 9 are met.
The core operational limit applies only when the reactor is critical.
- The heatup and cooldown rate restrictions applicable when the temperature of one or more of the PCS cold legs is less than 450°F are consistent with the analyses performed for low temperature overpressure protection (LTOP) (References 13 and 14). At 450°F or above, the PCS safety valves provide overpressure protection for heatup or cooldown rates_:: 100°F/hr."
I. Section 3.1.8 is completely revised to change PORV setpoints and increase the temperature range where LTOP is applicable.
J. Section 3.3.2g is revised to read:
"g. The control fuses for the high pressure safety injection pump (P-66A and P-66B) motors shall be removed when the temperature of one or more of the primary system cold legs is < 430°F unless the reactor head is removed.
K. The last paragraph of the Basis for section 3.3 is revised to read:
II Removal of the control fuses for the HPSI pumps eliminates excessive PCS mass additions due to inadvertent pump starts.
HPSI pump starts in conjunction with a charging/letdown imbalance may cause 10CFRSO Appendix G limits to be exceeded when the PCS temperature is < 430°F. When the PCS temperature is > 430°F, the pressurizer safety valves ensure that *the PCS pressure will not exceed 10CFRSO Appendix G limits when one or both HPSI pumps are started."
L. Section 4.1.lc has been added to provide a surveillance requirement when open PORV pilot valves are used as an alternative to venting the PCS.
M. Sections 4.6.la and b have been combined as Section 4.6~1a and Section 4.6.lc has been designated Section 4.6.lb and revised to read:
"Both high pressure safety injection pumps shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the temperature of one or more of the PCS cold legs is < 430°F by verifying that the control system fuses and their .fuse holders for the HPSI pump
'breakers (P66A, P66B) have been removed from the circuit."
OC1287-0234-NL04
3 N. The paragraph below has been added to the basis of Section 4.6 to give the basis for the surveillance requirement to verify that both HPSI control fuses are removed when the PCS temperature is < 430°F.
"Unless the reactor head is removed, the control fuses for both HPSI pump breakers are removed from the circuit when the PCS temperature is < 430°.F to prevent a mass addition and the accompanying PCS pressure increase which would result if a HPSI pump were started.
That resultant pressure increase could cause the pressure limits required by 10CFR50 Appendix G to be exceeded."
II. Discussion The above proposed Technical Specifications changes will provide Low Temperature Overpressure Protection (LTOP) and prevent the 10CFR50.
Appendix G heatup and cooldown pressure limits from being exceeded.
Above 430°F, the pressurizer safety valves prqvide overpressure protection. Three conditions are recognized which could cause the primary coolant system (PCS) pressure to exceed the 10CFRSO Appendix G limits. They are:
- 1. A mass addition caused by the start of a high pressure safety injection (HPSI) pump,
- 2. A mass addition resulting from a charging/letdown imbalance,
- 3. An energy addition caused by the initiation of -forced circulation when the steam generator temperature is greater than the cold leg temperature of the PCS.
A mass addition by a HPSI pump and the concurrent pressure increase is prevented in proposed section 3.3.2g by the requirement for both HPSI pump motor control fuses to be removed when the PCS temperature is below 430°F unless the reactor head is removed.
The setpoints of the Power Operated Relief Valves (PORVs) as required by proposed Sections 3.l.8a and 3.1.Bb have been shown by analysis (Reference 1) to be low enough to prevent the pressure increase resulting from the maximum possible charging/letdown imbalance (three charging pumps operating and letdown isolated) from causing the PCS pressure to exceed the 10CFRSO Appendix G heatup and cooldown pressure limits.*
Analysis (Reference 2) has been completed which shows that the maximum possible charging/letdown imbalance will not cause the 10CFRSO Appendix G pressure limits to be exceeded when the PCS temperature is greater than 385°F, a bubble is formed in the pressurizer and the actual pressurizer liquid level is less than 60%. Proposed section 3.1.Bc allows the PORVs to be inoperable when these conditions exist. Forming a bubble of appropriate size and rendering the PORVs inoperable facilitates operation by increasing the size of the operating pressure/
temperature window.
OC1287-0234-NL04
4 ACTION steps "a" and "b" are similar to the Standard Technical Specifications except the option of opening the pilot valves and block valves for both PORVs has.been added. Analysis (Reference 1) has been completed which shows that if a single PORV is open at 310 psia, a charging/letdown imbalance will not cause the 10CFRSO Appendix G pressure lim~.ts to be exceeded.
The proposed requirement in Section 3.1.lh for the steam generator temperature to be less than or equal to the PCS cold leg temperature before a primary coolant pump is started to initiate forced circulation unless the PCS cold leg temperature is more than 450°F eliminates the possibility of an energy addition caused by the initiation of forced circulation. Above 450°F, an energy addition to the PCS resulting from the initiation of forced circulation will not cause the 10CFRSO Appendix G pressure limits to be exceeded because the PCS safety valves provide adequate overpressure protection.
- Proposed Sections 3.l.2a, b, and c. are necessary to restrict heatup and cooldown rates at low temperatures to rates for which the pressure limits of 10CFRSO Appendix G, as illustrated in Figures 3-1, 3-2 and 3-3 of Section 3.1.2, are above the maximum pressures which could result from a possible transient. Proposed Section 3.l.2d restricts the pressurizer heatup rate to maintain the PCS within the analyzed conditions (Reference 2).
The proposed changes in Sections 4.1.lc, 4.6.lc and the basis for
~Section 4.6 align the Surveillance Requirements with the proposed Limiting Conditions for Operation.
Therefore, through a combination of PORV setpoints, equipment inoperability requirements, and restrictions on the primary/secondary temperature relationship when initiating forced circulation in the PCS, the proposed Technical Specifications prevent the pressure limits of the 10CFRSO Appendix G curves from being exceeded.
References
- 1. Analysis for E-PAL-87-lOlG "Calculation of PCS Pressure Increase From Adding 133 gpm (3 charging pumps) Before the PORVs Open,"
November 4, 1987.
- 2. Analysis for E-PAL-87-lOlG " Palisades Heatup and Cooldown Curves",
November 4, 1987.
III. Analysis of No Significant Hazards Consideration Consumers Power Company finds that activities associated with this change request involve no significant hazards, and, accordingly, a no significant hazards determination per 10CFRS0.92(c) is justified. The following evaluation supports that finding.
OC1287-0234-NL04
5 Evaluation
- 1. Involve a significant increase in the probability or consequences an accident previously evaluated LTOP prevents the PCS pressure from exceeding 10CFRSO. Appendix G pressure/temperature limits. Three recognized conditions could cause those limits to be exceeded. Two involve mass additions i.e.,
HPSI pump start and a charging/letdown imbalance. The third involves an energy addition - i.e., the initiation of force~ PCS circulation when the steam generator temperature is greater than the PCS temperature.
This proposed Technical Specification change prevents those conditions from occurring by:
- 1. Requiring the HPSI pump control fuses to be removed below 430°F,
- 2. Requiring the PORVs to be* operable (unless T ' > 385 °F and a PZR bubble > 40% is formed) up to 430°F, andpcs
- 3. Requiring the steam generator temperature to be equal to or less than the PCS temperature when forced PCS circulation is initiated unless the PCS temperature is high enough to allow the PCS safety valves to provide overpressure protection.
Therefore, the probability of exceeding allowable pressures is decreased. The consequences of an accident (rupturing the pressure barrier) remain the same.
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated The proposed changes only lower the pressure relief setting over the temperature range previously protected by LTOP, extend LTOP to higher temperatures, and add precautionary measures during heatup and cooldown. Thus, they do not create the possibility of a new or different kind of accident *.
- 3. Involve a significant reduction in a margin of safety The margin of safety is the difference between the stress at which the PCS pressure boundary could fail and the stress permitted by 10CFR50 Appendix G. This change ensures that the stress permitted by 10CFR50 Appendix G is not exceeded. Therefore, it does not
- involve a reduction in a margin of safety.
IV. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no significant hazards consideration. This change has also been reviewed OC1287-0234-NL04
6 under the cognizance of the Nuclear Safety Board. A copy of this Technical Specification Change Reguest has be~n sent to the State of Michigan official designated to receive such Amendments to the Operating License.
CONSUMERS POWER COMPANY By Sworn and subscribed to before me this 22nd day of December 1987.
~*t~
Elaine E Buehrer, Notary Public Jackson County, Michigan My commission expires October 31, 1989 OC1287-0234-NL04