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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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- 1 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. Section 3.1.lh is revised to ensure an energy addition to the PCS I will not occur when forced circulation is initiated at low PCS I temperatures (see page changes). I I
B. The last paragraph in the Basis for section 3.1 is revised to I explain why precautions against a PCS energy addition are only I required at low temperatures (see page changes). I I
C. S~ction 3 .1. 2a has been revised to restrict heatup rate limitaticms I at low temperatures (see page changes). I I
D. Proposed Section 3.l.2b has been revised to restrict cooldown rates I at low temperatures (see page changes). I I
E. Section 3.1;2c has been revised to include the heatup and cooldown I rate restrictions as proposed in Section.3.l.2a and b (see page I changes). I I
F. Section 3.1.2d has been revised to restrict the pressurizer heatup I rate (se~ page changes). I I
G. Two paragraphs have been proposed at the end of the Basis for I Section 3.1.2 to explain limitations placed on heatup and cooldown I rates (see page changes). I I
H. Figures 3-1 and 3-3, the pressure/temperature limits for heatup I and hydro, have been revised to allow higher pressures at a given I temperature. Figure 3-2, pressure/temperature limits for I cdoldown has been revised in format only to maintain consistency I with the format of Figures 3-1 and 3-3 (see page changes). I I
I. Section 3.1.8 is completely revised to change PORV setpoints, I increase the temperature range.where LTOP is applicable and I provide an alternate method of venting the PCS (see page changes). I I
J. Section 3.3.2g is revised to enhance protection against core damage I if a loss of coolant accident would occur while the reactor is I subcri!tical; and>i at the same time, ft ensures that Appendix G I
,~~;:;-;~~:;;-;;~::-::--=~=---=--===--'--~~-
OC0288-0039-NL02 ' 0004250194 00041:21~ '
I PDR ADOCK 05000'255 I P PDR
~.
2 heatup and cooldown limits will not be exceeded while requiring one I HPSI pump to be operable above 350°F, two HPSI pumps to be operable -I above 460°F, and a dedicated operator if the PORV's are not operable I above 385°F and less than 430°F. In addition, a choice of method of I insuring HPSI inoperability is allowed to permit pump testing (see I page changes). I I
K. The last paragraph of the Basis for section 3.3 is deleted and four I paragraphs added to include the basis for HPSI operability require- I ments in certain PCS temperature ranges, for the requirement to have I 1
a d edicated operator and for the exceptions to the requirements of I Section 3.0.3 (see page changes). /
I L. Section 4.1.lc has been added to provide a surveillance requirement I when open PORV pilot valves are used as an alternative to venting I the PCS (see page changes). I I
M. Sections 4.6.la and b have been combined as Section 4.6.la and a I new Section 4.6.lb has been added to ensure both HPSI pumps are I inoperable when the PCS temperature is less than 300°F (see page I changes). I I
II. Discussion The above proposed Technical Specifications changes will provide Low Temperature Overpressure Protection (LTOP), enhance protection against core damage resulting from a subcritical loss of coolant accident (LOCA), and prevent the 10CFRSO Appendix G heatup and cooldown pressure limits from being exceeded. Above 430°F, the pressurizer safety valves provide overpressure protection. Three conditions are recognized which could cause the primary coolant system (PCS) pressure to exceed the 10CFR50 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 I limited in proposed section 3.3.2g by the requirement for both HPSI I pumps to be inoperable when the PCS temperature is less than 300°F I unless the reactor head is removed and by requiring that only one HPSI I pump be operable when the PCS temperature is equal to or more than I 350°F and is less than 430°F. I I
OC0288-0039-NL02
,J 3
The setpoints of the Power Operated Relief Valves (PORVs), as required I
- -- by proposed -sections 3; 1. 8a and 3 .1. 8b, have been shown by analysis I (References 1, 2 & 3) to be low enough to prevent the pressure increase I resulting from the maximum possible charging/letdown imbalance (three I charging pumps operating and letdown isolated) plus a one pump HPSI from I causing the PCS pressure to exceed 10CFR50 Appendix G heatup and I cooldown pressure limits. I I
Analysis (Reference 4) has been completed which shows that the maximum I possible charging/letdown imbalance plus inadvertent HPSI operation I will not cause the 10CFRSO Appendix G pressure limits to be exceeded I when the PCS temperature is greater than 385°F, a bubble is formed in /
the pressurizer, the actual pressurizer liquid level is less than 60%, I and a dedicated operator takes mitigatory action within 2.9 minutes. I Proposed section 3.1.8c allows the PORVs to be inoperable when these I conditions exist. Forming a bubble of appropriate size and rendering I the PORVs inoperable facilitates operation by increasing the size of I the operating pressure/temperature window. Proposed Section 3.3.2 I requires a dedicated operator. I I
ACTION steps "a" and "b" of Section 3.1.8 are similar to the Standard I Technical Specifications except the option of venting the PCS by opening I the pilot valves and block valves for both PORVs has been added. I 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 10CFR50 Appendix G pressure limits 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 a low temperature energy addition caused by the initiation I of forced circulation. Above 450°F, an energy addition to the PCS resulting from the initiation of forced circulation will not cause the 10CFR50 Appendix G pressure limits to be exceeded because the PCS safety valves provide adequate overpressure protection.
Proposed Sections 3.1.2a, b, and c. are necessary to restrict heatup and cooldown rates to those rates for which the pressure limits of 10CFR50 I 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).
_Proposed ch?nges to the heatup and hydro pressure/temperature limits in I Figures 3-1 and 3-3 of Section 3.1.2 are the result of the deletion of I non-required conservatisms. The proposed limits were derived using Reg I Guide 1.99 draft Revision 2 correlations and remain in compliance with I Appendix G of 10CFR50. The proposed changes have been informally I reviewed by the NRC staff and are the basis for administrative LTOP I and low temperature ECCS requirements as described in our January 20,. I 1988 and January 22, 1988 submittals. Reference 5 contains the analysis I which determines pressure and temperature limits. I OC0288-0039-NL02
4 The proposed changes in Sections 4.1.lc, 4.6.lb and in 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 operability requir~ments, 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 10CFR50 Appendix G curves from being exceeded.
References
- 1. EA-PAL-85-101 "Calculation of PCS Pressure Increase From Adding I 133 gpm (3 charging pumps) Before the PORVs Open," November 4, 1987. I I
- 2. EA-PAL-LTOP-880119 "Calculation of Required PORV Capacity to maintain /
the PCS Below Appendix G", January 20, 1988. I I
- 3. EA-PAL-LTOP-880120 Rev A - "PORV Flow Capacity at Expected LTOP /
Conditions" February 15, 1988. I I
- 4. EA-PAL-LTOP-880121 - "Calculation of Time for Operator to Act for l HPSI and Bubble" January 20, 1988. I I
- 5. EA.:.RBJ-RWS-"Palisades Reactor Pressure Vessel Temperature Limits /
Determination", April 4, 1988. /
I 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 10CFR50.92(c) is justified. The following evaluation supports that finding.
Evaluation
- 1. Involve a significant increase in the probability or consequences an accident previously evaluated LTOP prevents the PCS pressure from exceeding 10CFR50. Appendix G pressure/temperature limits. Three recognized conditions could cause those limits to be exceeded. Two involve mass additions i.e.,
an inadvertent HPSI pump start and/or a charging/letdown imbalance.
The third involves an energy addition - i.e., the initiation of forced PCS circulation when the steam generator temperature is greater than the PCS temperature.
This proposed Technical Specification change prevents those conditions from causing Appendix G limits to be exceeded by:
OC0288-0039-NL02
" .* ,a_.
5
- 1. Requiring both HPSI pumps to be inoperable below 300°F, I requiring one HPSI pump to be inoperable below 430°F, and I
- 2. Requiring the PORVs to be operable (unless T > 385°F~ actual pressurizer level is less than 60%, and a deH~~ated operator is used) up to 430°F, and
- 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.
The PORV setpoint has been lowered and the temperature range over I which the PORV's provide protection has been extended. Therefore, I overall the probability of exceeding allowable pressures is *j decreased. The LOCA during heatup or cooldown has not been I evaluated nor has the NRC reviewed it using specific NRC guidance. I Thus, the proposed change does not increase the probability or I consequence of a previously evaluated accident. However, the. I proposed change does insure at least one HPSI pump available at I temperatures above 350°F to insure adequate heat removal. I
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated The proposed changes slightly raise the heatup pressure limits, I significantly lower the pressure relief setting, extend LTOP to I higher temperatures and add precautionary operator monitor measures I during heatup and cooldown. None of these changes create a new or I different kind of accident from that previously evaluated for LTOP. I I
There has been no LOCA evaluated for plant conditions during heatup. I or cooldown, thus, no change to previous evaluations. The proposed I change is to insure LOCA protection equipment operability and revise I LTOP setpoints. Maintaining LOCA equipment operable over an I extended plant operating mode could change the probability of a I low temperature overpressure accident but does not create the I possibil~ty 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 10CFRSO Appendix G. This change does not change the stress allowed by 10CFRSO Appendix G and ensures that the stress allowed by .10CFRSO Appendix G will not be exceeded. Therefore, it does not involve a reduction in.a margin of safety.
OC0288-0039-NL02
6 IV. Conclusion
- The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that this change does not involve an unrevi.ewed safety question and therefore involves no significant hazards consideration. This change has also been reviewed under the cognizance of the Nuclear Safety Board. A copy of this Technical Specification Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.
CONSUMERS POWER COMPANY By~ David P Hoffman, i Nuclear Operations Sworn and subscribed to before me this 12th day of April 1988.
Elaine E Buehr r, otary Public Jackson County, Michigan My commission expires October 31, 1989 OC0288-0039-NL02