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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] |
Text
Kenneth W Berry
_____ ___ ---------~- ____ Director _______ -- -- ------- - - - --
Nuclear LJce~ing General Offices: 1945 West Parnall Road,* jackson, Ml 49201 * (517) 788-1636 March 25, 1986 Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
TECHNICAL SPECIFICATION CHANGE REQUEST REVISION -
ADDITION OF 480 V DISTRIBUTION BUSES, REDISTRIBUTION OF MCC'S AND MISCELLANEOUS REVISIONS TO SPECIFICATION 3.7 Attached are three (3) originals and thirty-seven (37) conformed copies of a proposed change to the Palisa_des Technical Specification which supersedes a previous proposed change submitted on April 10, 1984. The proposeq change concerns the addition of 480 V distribution buses 19 and 20 which were added to provide class lE power for the new Control Room heating ventilating and air conditioning system. Also, new Motor Control Centers (MCC's) were added and are being powered from the buses. Due to the addition of the new buses, certain ~CC's have been redistributed to other 480 V distribution buses.
tn addition to these changes, the LCO statement of Specification 3.7.2 has been revised such that it will apply above primary coolant temperature of
.325°F rather than above reactor criticality. Two new LCO conditions were.
added to Specification 3.7.2 to address the fuel oil storage tank level and*
the fuel oil transfer pumps. Also included in this change requ~st are several editorial changes and corrections to Specification 3.7 and its Basis.
A check in the amount of $4,000 was attached to the April 10, 1984 letter.
Kenneth W B.erry Director, Nuclear Licensing
'
CC Administrator', Region III, USNRC NRC Resident Inspector - Palisades Attachment
1
. ---CONSUMERS POWER GOMPANY- - - - -*.
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. Delete existing item 3.7.l(e) and add the following new item, as 3.7.l(e):
"480 V distribution buses 19 and 20.".
B. Re-letter existing items 3.7.l(f) through (1), as 3.7.l(h) through
.(n).
C. Add the following new item, as 3.7.l(f):
"MCC numbers 1, 2, 25 and 26."
D. Add the following new item, as 3. 7. 1 (g):
"MCC numbers 7, 8, 21, 22, 23 and 24."
E: Revise newly re-lett~red item 3.7.l(h) as follows:
"125 V d-c buses DlO and D20" F. Revise newly re-lettered item 3.7.l(i) as follows:
"Four preferred a-c buses YlO, Y20,_Y30 and Y40."
G.* Revise newly re-lettered item 3.7.l(k) as follows:
"Both diesel generators, with a minimum of 2500 gallons of fuel in each day tank, a minimum of 16,000 gallons of fuel in the underground storage tank, and at least one fuei oil transfer pump."
H. Revise newly re-lettered item 3.7.l(m) as follows:
"240 V a-c power panels No 1 and 2, and their associated Air Blast Circuit Breaker (ABCB). distribution systems, which are located in the switchyard."
TSOP0386-0002A-LI01-NL04
2 I. ~-:.~is~ ~l}_e_U_r.i;t sentence .oLSpec-if-ica-tion -3~ 7.-2--as-*follows: -- - -- --
- "With the primary coolant system at a temperature greater than 325°F, the requirements of Specification 3.7.1 may be modified to permit one of the following conditions to exist."
J-. Delete existing item 3. 7. 2(e) and add the following new item, as 3.7.2(e):
"-480 V distribution bus 19 or 20 may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no ~noperable safety feature components associated with the operable bus."
K. Re-lettei existing items 3.7.2(f)-throu~h (m), as 3.7.2(h) through
( 0)
- L. Add the following new item, as 3.7.2(f):
- "MCC 1 and 25 or 2 and 26 may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable safety feattire components associated with the_ operable pail- of MCCs."
M. Add the following new item, as 3. 7-. 2 (g):
MCC 7, 21 and 23 or 8, 22 and 24 may be inoperable for up to 8_ hours provided there are_ no inop~rable safety feature components associated with the operable trio of MCCs."
N. Reyise newly re-lettered item 3.7.2(h) as follows:
"125 V d-c bus DlO or D20 may be inoperable *.. inoperability of the D20 bus."
- 0. Delete the asterisk in newly re-lettered item 3.7.2(k), as well as the corresponding outdated footnote. Also change "any month" to "any 30-day period," as follows:
" ... to 7 days (total for both) during any 30-day period, II
--
P. Revise newly re-lettered item 3.7.2(o) as follows:
- "The switchyard 125 V d-c power ... "
Q. In newly lettered items 3.7.2(1) and (o), change "ACB breakers" to "Air Blast Circuit Breakers (ABCBs)" (1 instance), and change "ACB breakers" to "ABCBs" (5 instances).
TSOP0386-0002A-LI01-NL04
3 R. Add
---
the follow;i.J:lg __n_ewi_t_em,
-* -- ~--- --- .
_as_-3.7.2(-p)-:-
.
- -
"The contents of the underground fuel oil storage tank may be between 16,000 gallons and 10,000 gallons for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />."
S. Add the following new item, as 3. 7.2(q):
"Both fuel oil transfer pumps may be inoperable for _16 hours."
T. Revise the Basis section of 3.7 as follows:
- 1. Change the second and third ientence of paragraph one to:
"The 480 V equipment is arranged on four buses. The 2400 V equipment ls supplied from two buses."
- 2. Replace the second and third sentences of paragraph 2 with:
"To supplement the standby power source, a spare 345-2.4/4.16 kV, 25 MVA transformer is installed and can be connectt2)in place of a start-up transformer within 3 days. "
- 3. In paragraph 4,. se~ond sentence, change "3.2.2" to "3.1.2".
- 4. In paragraph 5, change the first sentence, to:
"Equipment served by the engineered safeguards buses is arranged so that loss ... "
- 5. In paragraph 6, change the first sentence to:
"The requirements for MCC No 1, 2, 7, 8, 21, 22, 23, 24, 25 and 26 as well as the 480 V distributicin buses 11, 12, 19 and 20 will assure availability of ... "
- 6. In paragraph 6, second sentence, change "buses No. 1 and No. 2" to "buses DlO and 020"
- 7. In paragraph 7,_change the *first and second sentences to:
'.'The required minimum fuel o:i,.l availability of 2500 gallons in each diesel's day tank is considered adequate since approximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> running time (worst case loading) ~s available before transfer to fuel oil from the storag-e tank .
is mandatory. The fuel oil transfer pumps are used for transferring fuel oil from the storage tank to the day tanks."
- 8. In paragraph 7, fourth sentence_, change "7 days" to "6 days".
- 9. In paragraph 8, second sentence, change "ACB breakers" to "Air Blast Circuit Breakers (ABCBs)".
TSOP0386-0002A-LI01-NL04
.4
- 10. In- . paragraph 10 *- chii_I!gt?_ '~l!_n_H~'-to_ "diesel--gene-Fa-tors~
-- - - -- - - -- -
- - - -
- 11. Under References make the following changes:
"(2) FSAR Update Section 8.1"
"(3) FSAR,_Section 8.3.2 and 8.4
"(S) FSAR, Section 8.4.1.3."
II. Discussion:
A. MCCs 1 and 2 are being powered from the new 480 V b.uses 19 and 20 to alleviate overloading of 480 V buses 11 and 12. They are no longer associated with the conditions for MCC 7 and 8. Class lE MCCs 21, 22, 23 and 24 should now be associated with conditions for MCC 7 and 8. 48-0 V distribution buses 19 and 20 were added to provide Class lE power for the new control room HVAC sy'stem and future lE loads. MCCs 25 and 26 were aaded to power the HVAC loads.
B. Renumbering items
- c. Rearranged for clarity, also see "A" above.
D. Rearranged for clarity; also see "A" above.
E. Editorial change, to utilize the equipment names as found. on plant drawings.
F. Editorial change to add specific equipment descriptors.
G. The specification is revised with an additional requirement that at least one fuel oil transfer pump be operable. The.fuel oil transfer pumps were not previously addressed in Chapter 3 of the Palisades Technical Specifications.
H. Editorial change stating the switchyard as the location of the equipment.* Additionally, an editorial change revising the breaker description from ACB (air-circuit-breaker) breaker to Air.Blast Circuit Breaker (ABCB) has been made to.reflect the correct terminology and more_ accurately describe the breakers.
I._ The change in the LCO statement of Specification 3. 7. 2 is requested to provide alignment between Specifications 3.7.1 and.
3.7.2. Currently, 3.7.1 requires various electrical components to be operable prior to the primary coolant system-exceeding- 325°F.
Specification 3.7.2 currently allows the requirements of Specification 3.7.1 to be modified to the extent that one exception may be allowed after the reactor has been made critical.
For conditions between 325°F and critical (hot shutdown), a literal interpretation of current Technical Specifications would require Specification 3.0.3 to be invoked if any one of the TSOP0386-0002A-LI01-NL04
5 conditions of Specifi~_{ition_J.-7 .L -was--not;-met-_. When- oeiow ____ _
:- ---* -- -- crrtkar, -th_e_ plarrt-- is in a more conservative condition than when critical, however, when critical .or above, Specification 3.7.2 allows more latitude through the specified LCO conditions.
Consequently, specifying. 325°F for both 3.7.1 and 3.7~2 resolves an unnecessary conservatism, and is in accordance with CE Standard Technical Specifications.
J. The added buses and MCCs have been provided LCOs consistent with existing Technical Specifications. See "A" above.
K. Renumbering items.
L. See "J" above.
M. See "J" above.
N. Editorial change, to utilize tbe equipment names as found on plant drawings.
O. Editorial change to clarify that month can apply to any 30-day period.
?* - Editorial change stating switchyard as location of the equipment.
Q. See "H" above.- Editorial change of air circuit breaker to air blast circuit breaker; R. This item has been added to provide an LCO of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in the event the contents of the fuel oil storage tank fall below 16,000 gallo~s, but con~ains at least 10,000 gallon~. Existing Technical Specifications do not address the situation of less than 16,000 gallons of fuel oil in the storage tarik, thus requiring Technical Specification 3.0.3 to be entered. even th~ugh sufficient fuel oil for more than 4 days of diesel generator operation (under worst case loading) is still availa~le with the remaining fuel oil (10,000 gal+ 2,500 gal in day tank). Therefore, an Lco*of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provides operator flexibility, while not compromising plant safety.
S. This item has been added to provide an LCO of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in ~he event that neither fuel oil transfer pump is operable. Fuel oil day tank capacity is sufficient for at least 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of diesel generator operation before additional fuel would have td b~
transf~rred from th-e underground storage tank. Existing Technical Specifications do not address the *operability iequirements of the fuel oil transfer pumps, other than through a monthly surveillance requirement in Section 4.7.l(e).
TSOP0386-0002A-LI01-NL04
6 T. (1) Editorial change (2) Updated wording from the Palisades FSAR is substituted for the out of date information.
(3)' Editorial change to correct the refeience to the appropriate Technical Specification 3.1.2.
(4) Editorial change to clarify the intent.
(5) Editorial change to add additional MCC's and distribution buses.
(6) Editorial change for consistent nomenclature with plant drawings.
(7) Technical Specification 3.7.1 requires only 2500 gallons of ftiel oil in the day tanks and.16,000 gallons in the stor~ge tank. Therefore it is inappropriate to describe a higher capacity and a correspondingly longer run time. The foilowing sentence has been clarified to reflect actual operational requirements of the fuel oil transfer pumps.
(8) Since the diese_l generator day tanks do not necessarily
- contain more than 2,500 gallons, the day tank contents plus the storage tank contents provide approximately 6 days of run time rather than the stated 7 days.
(9) The breakers are Air Blast Breakers vice Air Circuit Breakers.
(10) Editorial change to clarify the sentence.
(11) Editorial changes to References.
Analysis of No Significant Hazards Consideration The subject proposed Technical Specifications changes concern the following four items:.
- 1. The addition of 480 V distribution buses 19 and 20 and the corresponding redistribution of loads of MCC's (physically installed and operational for start-up following the 1983/1984 refueling outage).
- 2. A revision of the LCO statement of Technical Specification 3.7.2 to apply above 325°F, rather than critical.
- 3. The addition of two new LCOs to Technical Specification 3.7.2, for fuel oil storage tank level and fuel oil transfer* pump operability.
TSOP0386-0002A-LI01-NL04
7
- 4. Editorial clarifications and c_or_r_e~~_i_on~ to the 3 .7 -Basis.---*---- - -
Item 1. reflects the addition of new 480 V distribution equipment and physical redistrib~tion of MCC's to reduce loads ori ~ther buses, and is
.fully consistent with the format and intent of existing Technical Specifications. It also corrects several editorial deficiencies. The change request adds the new distribution buses and MCC's to the Technical Specifications. This administrative change to the Specifications maintains consistency with the existing Specifications and does not involve an increa*se in the probability or consequences of an accident nor create a new or different kind of accident. No margin of safety is affected by this change to the Technical Specifications.
Item 2. provides needed*alignment between Specifications 3.7.1 and 3.7.2. Currently, 3.7.1 requires various electrical components to be operable prior to the PCS exceeding 325°f. Specification 3.7.2 allows the requirements of Specification 3.7.1 to be modified to the extent that one exception may be allowed after the" reactor has been made critical. The condition between 325°F an~ critical is, therefore, not addressed. Since when subcritical, the plant is in a more conservative condition than when above critical (based on* theory of all existing Technical Specifications which require transgression to successively lower reactor operating conditions as being inherently more *
- conservative)~ it follows that the latitude currentli afforded through the specified LCO condition of 3.7.2 when the reactor is above critical should also apply above 325°F. Consequently, specifying 325°F for 3.7~2 as well.as 3.7.1 provides specific guidance while the plant is between 325°F and critical and is consistent with CE Standard Technical Specifications. The revision adds consistency between the specifica-tions and no margin of safety is affected. Therefore no significant increase in the probability or consequences of an accident is created and the proposed specification.does not create the possibility of a new or different kind of accident.
- Item 3. allows a 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO when the fuel oil storage tank is between 16,000 gallons and 10,000 gallons. Existing Technical Specifications do not address the situation of less than 16,000 gallons in the tank, requiring Specification 3.0.3 to be entered, evei though sufficient fuel oil for more than 4 days of diesel generator operation (worst case loading) is available with only 10,000 gallons in the storage tank and .
the minimu~ day tank volume of 2~500 gallons. Therefore an LCO of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> does not impact plant safety, while providing a level of operator flexibility. A second LCO of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> when neither fuel oil transfer pump is available, along* with a new requirement that at .least one pump be operable prio~ to exceeding 325°F provide operating requirements where none were previously specified. Since over 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of run time is available with the minimum day tank level, 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> for the fuel oil transfer pump LCO does not impact plant *safety, while providing needed guidance to the operators regarding pump operability.
The defining of the above noted requirements does not involve a significant increase in the probability or consequences of an ~ccident TSOP0386-0002A-LI01-NL04
- 8 nor do they create a new or different kind of__ a_<;<;ident -than--previotiSly- --
evaluat~g. _ No__margin-of-saf*ety has_oe-en-- reduced with the proposed
-specffication.
Item 4. is primarily editorial in nature. The Basis section was changed to more ac_curately reflect the specified minimum conditions of 3.7.1 with respect to fuel oil capacities and corresponding diesel generator run times. These changes to the Basis do not involve a significant increase in the probability or consequences of an accident nor do they create the possibility of a new or diffe~ent kind of accident from any previously evaluated. Although changes were made which clarify the Basis with respect to available fuel oil capacity and.
corresponding run times, these assume the same consumption-rate as found in the FSAR, along with the minimum fuel oil capacities specified by Technical Specification 3.7.1. Therefore.no significant reduction in the margin of safety has occurred.
- III. Conclusion The-Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that this change does. not involve an unrevtewed safety question and therefore involves no significant hazards consideration. _This change has also been reviewe_d
_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 .
Buckman, . Vice Presi Nuclear Operations Sworn and subscribed to before me this 25th day of March 1986.
Elaine*E Buehrer, Notary Public Jackson County, Michigan My commission expires October 31, 1989 *-,~
TSOP0386-0002A-LI01-NL04
ATTACHMENT Consumers Power. Company Palisades Plant *
- -------- *- --~-- --~-
-:----- ~ --- ~ - . Docket 50-255 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES March 25, 1986 5 Pages .
IC0386-0046-NL04