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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 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 4.1.1.a.3 to read as follows:
"Performance of a channel calibration on the PORV actuation channel at least once per refueling cycle."
B. Replace Table 4. 1.1 with the re vi s~d Table 4 .1.1, "Minimum Frequency for Checks, Calibrations and Testing of Reactor Protective System".
C. Replace Table 4 .1. 2 with the revised Table 4 .1. 2, "Minimum Frequency for Checks, Calibration and Testing of Engineered Safety Feature Instrumentation Controls".
D. Replace Table 4 .1. 3 with the revised Table 4 .1. 3, "Minimum Frequency for Checks, Calibrations and* Testing of Miscellaneous Instrumentation and Controls".
E. Revise the first sentence of Section 4.7.1.c to read:
" .* ', . at least once per refueling cycle during plant shutdown."
F. Revise the first sentence of Section 4.16.1.c to read as follows:
"At least once per refueling cycle . "
G. Revise the fifth paragraph of Section 4.16.i, Basis, to read:
~
!;* . .. " * *
- shutdowns at least once per refueling cycle."
H. Revise Section 4.17.2.2.d to read:
"At least onc.e per refueling cycle during shutdown*, by . . . "
I. Revise Section 4.17.5.1 to read:
"Each of the penetration fire barriers shall be verified to be functional by a visual inspection at least once per refueling cycle and prior to declaring a penetration fire barrier functional following repairs or maintenance."
Revised Technical Specification pages are attached. Proposed changes are shown by a vertical line in the right-hand margin .
. ... *.... .J
CONSUMERS POWER COJ\1PANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 II. DISCUSSION The above proposed Technical Specifications changes are requested in order to prevent unnecessary plant shutdowns or the extension of outages for the sole purpose of performing Technical Specification Surveillance Tests. The Palisades Plant Surveillance Test Procedures (STP) identified in Attachment 1 are required to be performed on an 18-month cycle and during a cold shutdown condition. A few of the tests can be performed at hot. shutdown and power operation; however, it is Consumers Power Company's position that conducting surveillance requirements for critical instrumentation and controls during these plant conditions can impact the safe operation of the plant.
Consumers Pm.rer Company requests that the testing frequency for the STPs identified in Attachment 1 be changed such that these STPs can be performed anytime during each refueling cycle. An 18-month cycle is insufficient in duration to allow for the performance of Surveillance Testing during refueling outages only, even if the +/-25% criteria is utilized. The primary reason for this is due to the fuel reload design which was implemented during the 1979-80 refueling outage. The Palisades Plant was modified from approximately a 7500 Megawatt-Day per ton cycle to approximately a 10,000 Megawatt,...Day per ton cycle. This has resulted in approximately a five month extension to each fuel cycle.
With the equipment and component problems the Palisades plant experienced in the early stages of the current fuel cycle, the next refueling outage is now tentatively scheduled for August 13, 1983. This is 23~ months since the beginning of the last refueling outage (September 1980 to January 1981).
The due dates for the STPs listed in Attachment 1 will all occur before the scheduled date of the next refueling outage. And in most cases, the
+/-25% criteria will also be utilized prior to the next refueling outage.
In order to perform these STPs when they are due, we would.have to bring the plant down to a condition required to run the STPs. Putting the reactor through a shutdown transient just to perform these STPs is not considered justifiable.
Consumers Power Company has reviewed the results of the last three surveillance tests performed on the instrumentation and controls identified in Attachment 1 and determined that all of the systems or components were operable. In addition, the deviation and event reports generated as a result of these tests did not indicate any trends for potentially reoccuring systematic problems. It is our position that permitting the surveillance testing intervals to be dependent on the length of the fuel cycle will not jeop~rdize the plant nor the health and safety of the public. The testing frequency proposed by this submittal is consis-tent with the testing frequencies stated in Consumers Power Company's letters dated August 30, 1982 and November 5, 1982 entitled "Proposed Technical Specifications Request - Engineered Safety Feature Filtration System".
III. CONCLUSION Based on the foregoing, the Palisades Plant Review Cmmittee has reviewed this change and found it acceptable. Also the Nuclear Activities Plant Organization has reviewed the change under the cognizance of the Nuclear Safety Board and found it acceptable.
CONSUMERS POWER COMPANY BY ~];~i!H!e;/f Nuclear Operations Sworn and subscribed to before me this 5th day of May 1983.
My commission expires on 11/5/86.
SHERRY LYNN DURFEY Notary Pu~li~, Jackson County, ~~le,,
My Cornrn1ss1on Expires Nov. 5, 1986
) '
MI0583-0008A-NL02
Page 1 9f 6 ATTACHMENT 1 TECHNICAL SPECIFICATION "(T/S) APPLICABLE T/S LAST 3 TIMES TEST EQUIPMENT OPERABLE OR REMARKS SURVEILLANCE PROCEDURES SECTIONS WAS PERFORMED PARAMETER MEETS THE (Significant Deviation and Event APPLICABLE Reports Generat~d as a Result of T/S SECTIONS the Tests)
Refueling Calibration of 4.1.1.a.2 . 2/9/80 1 Yes.
PCS Overpressure Protection 9/14/81 Yes PCS Power Operated 4.1.1.a.4 12/4/79. Yes Relief Valves 11/2/81 11/09/81 Yes Safety Channel Linear Table 4.1.1.1.d 1/19/79. Yes Power Drawer Calibration 5/19/80 Yes 9/1/81 Yes Reactor Coolant Flow Table 4.1.1.3.b 4/10/78 Yes DR-PAL-78-013/3'Trip setpoints Channels Calibration 9/26/79 Yes out of tolerance in the 9/16/81 conservative direction ;
Thermal Margin/Low Table 4. 1.. 1. 4. b 9/16/79 Yes Pressurizer Pressure 11/2/80 Yes Channels Calibration 9/ 10/81 . Yes High-Pressurizer Pressure Table 4.1.1.5.b 4/ 11/78 Yes DR-PAL-78-029/Instrument drift -
Channels Calipration 9/17/79 Yes A periodic activity control 9/14/81 Yes sheet written to increase surveillance DR-PAL-80-089.~
The age of PT-:Ol02D caused normal instrument drift Steam Generator Level Table .4.1.1.6.b 4/10/78 Yes DR-PAL-78-035/Instrument drift 11/29/79 Yes of LT-0752B app~rent zero 11/12/81 Yes shift of-1.5%~ Past tests do not show any*systematic negative shift. DR-PAL-81-188/
Several instruments were found out of specified tolerances incorporated into lastest test revision.
TS0483-0001A-NL02 1
First Time Test Was Performed
. I .~
Page 2 qf 6 ATTACHMENT 1 TECHNICAL SPECIFICATION (T/S) APPLICABLE T/S LAST 3 TIMES TEST EQUIPMENT OPERABLE REMARKS SURVEILLANCE PROCEDURES SECTIONS WAS PERFORMED OR PARAMETER MEETS (Significant Deviation and Eyeht THE APPLICABLE Reports Generated as a Result of T/S SECTIONS the Tests.)
Low-Pressure SIS Table 4.1.2.1.b 3/2/78 Yes Initiation Logic Table 4.1.2.2.a 9/21/.79 Yes 9/20/81 Yes Engineered Safeguards Table 4.1.2.3.b 4/8/78 Yes DR-PAL-80-091/Whole system System Table 4.1.2.6.a 5/7 /80 Yes operated as it was designed Table 4.1.2.11.b 12/21/81 Yes to except the B charging ~
pump did not sta*rt on by-paP flow.
L Containment Area Table 4.1.2.5.b2 4/26/78 Yes Test results only pertain to the Monitor Calibration Table 4.1.3.4.b 11/7 /79 Yes Containment Isolation Monitors.
4/29/81 Yes The Containment High Range Monitors have not been declared operational.
3 Containment High Table 4.1.2.5.d3 4/15/78 Yes Radiation Test Table 4.1.2.7.a 5/3/80 Yes 3
Table 4.1.2.7.b 11/28/81 Yes Containment High- Table 4.1.2.4.b 4/2/78 Yes The 4/27/80 test had to be Pressure Spray Table 4.2.2.b performed twice. CV-0437A System Tests Table 4.2.2.13.c 4/27/80 Yes and CV-043B failed to open 4.6.1.a because the testors did not A 4.6.5.a 11/30/81 Yes wait long enough for the ti~
4.7.1.b delay to'time out. This portion of the test was re-run and valves operated satisfactorily.
Also, the right channel SIS alarm did not function properly however, the alarm serves no ,
safety function.
2 This section was changed to 4.1.3.4.a.b and 4.1.3.4.b.b by our T/S Change Request dated 11/5/82.
3 This section was changed to 4.1.3.4.b.d by our T/S Change Request dated 11/5/82.
TS0483-0001A-NL02
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.Page 3 o.f 6 ATTACHMENT 1 .-
TECHNICAL SPECIFICATION (T/S) APPLICABLE T/S LAST 3 TIMES TEST EQUIPMENT OPERABLE REMARKS SURVEILLANCE PROCEDURES SECTIONS WAS PERFORMED OR PARAMETER MEETS (Significant Deviation and Event THE APPLICABLE Reports Generated as a Result of T/S SECTIONS the Tests.)
SIRW Tank Level Table 4.1.2.12 2/28/78 Yes Switch Interlocks Test 5/6/80 Yes 9/22/81 Yes Safety Injection Tank Table 4.1.2.13.b 9/ 16/79 Yes DR-80-214/Equipment operable but Pressure Channel Calibration 12/1/80 Yes "as found" values were slightly 12/5/81 Yes with exceptions over tolerance. It was dee~
appropriate to change the T/S Surveillance Test.
During the 1981 refueling outage, not all of the test data met the acceptance criteria, however, major modifications were well under way in pan~l C-13.
Safety Injection Tank Table 4.1.2.13.b 9/16/79 Yes Pressure Switch Calibration 11/11/80 Yes 9/15/81 Yes Safety Inject;i.on Tank Table 4.1.2.13.b 9/16/79 Yes DR-PAL-79-125/Level indications Level/Channel Calibration 12/4/80 Yes and alarms out of tolerance.
12/22/81 Yes Alarm settings drifted in conservative direction. t.
Main Steam Isolation Table 4.1.2.16.b 4/1/78 Yes Valve Circuit Test 3/14/80 Yes 12/6/81 Yes SIRW Tank Temperature Table 4.1.2.17.b 8/ 1/79 Yes Indicator Calibration 11/5/80 Yes 9/1/81 Yes TS0483-0001A-NL02
Page 4 of 6 ATTACHMENT 1 TECHNICAL SPECIFICATION (T/S) APPLICABLE T/S LAST 3 TIMES TEST EQUIPMENT OPERABLE REMARKS SURVEILLANCE PROCEDURES SECTIONS WAS PERFORMED OR PARAMETER MEETS (Significant Deviation and Everit THE APPLICABLE Reports Generated as a Result of T/S SECTIONS the Tests.)
Control Rod Calibration Table 4.1.3.2.c 3/17/78 Yes Table 4.1.3.3.c 1/20/80 Yes 11/20/81 Yes ,,-
Pressurizer Level Table 4.1.3.7.b 10/2/79 Yes DR-PAL-78-019/Transmitter drifted Channel Calibration 12/9/80 Yes causing a 1-2% error. Past *
. 9/19/81 Yes history shows drift limited
__,2%. No further action taken.
DR-PAL-81-008/The acceptance
~riteria is violated for "as found" values on some of the units because of compensation incorporated to allow for static working pressure calibration shifts.
Control Rod Drive Table 4.1.3.8.a DR-PAL-82-120/The automatic System Interlocks Table 4.1.3.8.b 12/18/81 Yes and withdrawal prohibit alarm 5/9/82 Yes did not occur or reset within 8/ 13/82 Yes with exceptions the proper tolerance, however, auto rod motion is administra-tively prohibited.
Automatic Rod Withdrawal Table 4.1.3.8.a 12/5/81 Yes Prohibit Interlock Matrix Table 4.1.3.8.5 5/11/82 Yes 8/11/82 Yes Steam Generator Feedwater Table 4.1. 3.10 9/13/79 Yes Flow Instrument Loop 11/9/80 Yes Calibration 9/20/81 .,
Yes TS0483-0001A-NL02
I Page 5 of 6 ATTACHMENT 1 ,*
TECHNICAL SPECIFICATION (T/S) APPLICABLE T/S LAST 3 TIMES TEST EQUIPMENT OPERABLE REMARKS SURVEILLANCE PROCEDURES SECTIONS WAS PERFORMED OR PARAMETER MEETS * (Significant Deviation and Event THE APPLICABLE Reports Generated as a Result of T/S SECTIQNS the Tests.)
Containment Humidity Table 4.1.3.11 9/22/79 Yes DR-PAL-79-123/HT-1812 failed; 11/11/80 Yes transmitted, repaired and re-11/19/81 Yes calibrated. HT-1813, 1814 and 1815 tubes replaced following 11/11/80 test.
Narrow Range Pressure Indication/Shutdown Cooling
- Line Interlock Calibration Table 4.1.3.12 10/9/79 11/21/80 9/11/81 Yes Yes Yes e
Containment Service Table 4.1.3.13 9/10/79 Yes Water Break Detector 1/21/81 Yes DR-PAL-81-009/Equipment was 11/16/81 Yes operable but out of calibration.
It required a larger differ-ential pressure to actuate alarm.
Subcooled Margin 1 Table 4.1.3.18.b 12/7/81 Yes Monitor Surveillance Containment Hydrogen Table 4.1.3.22.b Has not been performed 1
Diesel Gene4a§or 4.7.1.c 10/21/81, 11/20/81 Yes Inspection ' 10/2/81, 11/8/81 Yes e Function Test Seismic 4/16/1 3/8/78 Yes Hydraulic Restraints 3/5/80 Yes 11/27 /81 Yes 4
TWo surveillance procedures.
5 The inspections are routinely performed in the Preventative Maintenance Program.
TS0483-0001A-NL02
Page 6 o.f 6 ATTACHMENT 1 TECHNICAL SPECIFICATION (T/S) APPLICABLE T/S .LAST 3 TIMES TEST EQUIPMENT OPERABLE REMARKS SURVEILLANCE PROCEDURES SECTIONS WAS PERFORMED OR PARAMETER MEETS (Significant Deviation and Event
- THE APPLICALBE Reports Generated as a result of T/S SECTIONS the Tests.)
Inspection and Preventive 4.17.2~2.d 10/10/79 Yes Maintenance of Fire 5/7 /80 Yes Pump Diesels 12/6/81 Yes Penetration Fire Barriers 1 4.17.5.1 4/18/80 Yes with exceptions ER-080-018/During inspection of Surveillance fire barriers bottom side of penetration H0-12 was missi~
12/15/81 Yes with exceptions The penetrations were open for modification~ in progress -
A fire watch was stationed. (
TS0483-0001A-NL02