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| ----*tbNSUMERS-POWER COMPANY. * --_______________ | | - ---*tbNSUMERS-POWER COMPANY. * -- _________________;__ |
| __;__ ( l DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS 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. CHANGE(s)
| | DOCKET 50-255 - LICENSE DPR PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS 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: |
| Delete Capsule A-60 from the Reactor Vessel Surveillance Coupon Removal Schedule and change Table 4.3.3, page 4-23 of the Palisades Technical Specifications to read as follows: Table 4.3.3 Reactor Vessel Surveillance CouEon Removal Schedule . Capsule Refueling Capsule 1 Target Removal Number Number Location (EFPY @ Refuel Primary Optional 23 A-240 2 Outside Core Barrel 2.26 @ W-290 5 11 Vessel Wall 4.33 @ 5 T-330 5 20 Above Core 4.33 @ 5 W-110 11 5 Vessel Wall 9.21 @ 11 W-100 20 25 Vessel Wall 16.5 @ 20 T-150 20 5 Above Core 16.5 @ 20 W-280 25 20 Vessel Wall 20.6 @ 25 W-260 35 39 Vessel Wall 28.7 @ 35 W-80 39 35 Vessel Wall 32.0 @ 39 1 Refer to Palisades FSAR, Volume 2, Section 4.5.3, Figure 4-11 for illustration of capsule locations 2 EFPY based on 2530 MWt power rating 3 2.26 EFPY from BCL 585-12 Report, March 13, 1979 8308100357 830803 PDR ADOCK 05000255 i I P PDR OC0583-0020B-NL02 Time 2 No) | | I. CHANGE(s) |
| L. ',f ------------u-;----nrscuss-roN A. Deletion of Analysis of Capsule A-60 The Palisades surveillance program contained two accelerated capsules (A-60 and A-240) and eight regular capsules. | | Delete Capsule A-60 from the Reactor Vessel Surveillance Coupon Removal Schedule and change Table 4.3.3, page 4-23 of the Palisades Technical Specifications to read as follows: |
| Capsule A-60 was scheduled to be removed during the second refueling outage, however, problems associated with the upper end fitting precluded removal in the reasonable length of time. Therefore, Capsule A-240, an equivalent capsule, was removed as allowed by Amendment 34 issued January 27, 1978. The analysis of Capsule A-240 that it has been exposed to a fluence of 4.4 x 10 nvt (E lMev) in 2.26 Effective Full Power Years (EFPY) of plant This was substantially greater than the 1.7 x 10 nvt (E lMev) value predicated for the second refueling outage. As of October 31, 1982, the Palisades reactor has operated for 4.47 EFPY based on a 2530 Mwt poy9r rating and 98,992,680 Mwht accumulated. | | Table 4.3.3 Reactor Vessel Surveillance CouEon Removal Schedule 1 2 |
| Assuming 4.4 x 10 nvt (E lMev) in 2.26 EFPY for Capsule A-240, the exposure of A-60 has been calculated to be approximately 8.7 x 10 nvt (E lMev). This value is greater than the predicted End of Life fluence (3.55 x 10 nvt, E lMev) to the vessel wall, therefore, no useful fracture toughness data would be obtained from the analysis of Capsule A-60. For this reason, Consumers Power Company requests that Capsule A-60 be deleted from the Palisades Reactor Vessel Surveillance Capsule Program. B. Request for Equivalent Capsule Withdrawal Option The Palisades Reactor Vessel Surveillance Program was designed to monitor radiation induced changes to the mechanical and impact properties of the reactor vessel and consists --of ten capsules containing base metal, weld metal and heat affected zone material representive of the pressure vessel. All of the capsules were inserted into their designated holders prior to the initial reactor startup. Eight of the capsules are arrayed in two groups 180 degrees apart at the midplane of the core and two capsules are in a low flux region above the core. Each capsule therefore, has a counterpart that is similar in type and quantity of samples located on the opposite side of the reactor core. Core geometry further enhances the similarity of a capsule and its counterpart by producing a neutron flux that is diametrically symmetrical about the circumfrence of the vessel wall. This condition ensures that, at any point in time, a capsule and its counterpart have been exposed to similar, if not OC0583-0020B-NL02 L. *_ft 3 --identical-0--neut-ron fluences-and-temperatu-res.- | | . Capsule Refueling Capsule Target Removal Time Number Number Location (EFPY @ Refuel No) |
| Based--on capsule type, location, content and environmental conditions the following capsules are considered to be essentially equivalent: | | Primary Optional A-240 2 Outside Core Barrel 2.26 @ 23 W-290 5 11 Vessel Wall 4.33 @ 5 T-330 5 20 Above Core 4.33 @ 5 W-110 11 5 Vessel Wall 9.21 @ 11 W-100 20 25 Vessel Wall 16.5 @ 20 T-150 20 5 Above Core 16.5 @ 20 W-280 25 20 Vessel Wall 20.6 @ 25 W-260 35 39 Vessel Wall 28.7 @ 35 W-80 39 35 Vessel Wall 32.0 @ 39 1 Refer to Palisades FSAR, Volume 2, Section 4.5.3, Figure 4-11 for illustration of capsule locations 2 EFPY based on 2530 MWt power rating 3 2.26 EFPY from BCL 585-12 Report, March 13, 1979 |
| T-330 & T-150 W-290 & W-110 W-100 & W-280 W-260 & W-80 A-60 & A-240* Consumers Power Company proposes that Table 4.3.3 (Reactor Vessel Surveillance Coupon Removal Schedule) be modified to provide the option of removing either the primary capsule or its equivalent. | | ( 8308100357 830803 i I PDR ADOCK 05000255 l P PDR OC0583-0020B-NL02 |
| Removal of an equivalent capsule will not reduce the effectiveness of the surveillance program and would be used only when difficulty in removing the primary capsule is encountered. | | |
| The added flexibility of this proposed option would reduce plant outage time and does not violate the requirement of Appendix H of 10 CFR Part SO. C. Analysis of No Significant Hazards Consideration The Palisades Plant Review Committee has concluded that the proposed changes discussed above do not involve an unreviewed safety question. | | L. ',f |
| In addition, the effectiveness of the reactor vessel surveillance program is not reduced and therefore the operation of the facility in accordance with the above proposed changes would not: 1. involve a significant increase in the probability or consequences of an accident previously evaluated; or 2. create the possibility of a new or different kind of accident from any accident previously evaluated; or 3. involve a significant reduction in a margin of safety. | | - - ---- -- - -- - u-;- -- -nrscuss-roN A. Deletion of Analysis of Capsule A-60 The Palisades surveillance program contained two accelerated capsules (A-60 and A-240) and eight regular capsules. |
| * Equivalent capsule removal provide for in Amendment No 34, January 27, 1978. Capsule A-240 was removed during the second refueling outage. OC0583-0020B-NL02 | | Capsule A-60 was scheduled to be removed during the second refueling outage, however, problems associated with the upper end fitting precluded removal in the reasonable length of time. Therefore, Capsule A-240, an equivalent capsule, was removed as allowed by Amendment 34 issued January 27, 1978. |
| * 4 III._ CONCLUSION | | The analysis of Capsule A-240 iny~cated that it has been exposed to a fluence of 4.4 x 10 nvt (E lMev) in 2.26 Effective Full Power Years (EFPY) of plant ~~eration. This was substantially greater than the 1.7 x 10 nvt (E lMev) value predicated for the second refueling outage. |
| ----------- | | As of October 31, 1982, the Palisades reactor has operated for 4.47 EFPY based on a 2530 Mwt poy9r rating and 98,992,680 Mwht accumulated. Assuming 4.4 x 10 nvt (E lMev) in 2.26 EFPY for Capsule A-240, the exposure of 1~apsule A-60 has been calculated to be approximately 8.7 x 10 nvt (E lMev). |
| The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that these changes do not involve an unreviewed safety question and consequently involve no significant hazards considerations. | | This value is significa~§ly greater than the predicted End of Life fluence (3.55 x 10 nvt, E lMev) to the vessel wall, therefore, no useful fracture toughness data would be obtained from the analysis of Capsule A-60. For this reason, Consumers Power Company requests that Capsule A-60 be deleted from the Palisades Reactor Vessel Surveillance Capsule Program. |
| This change has also been reviewed under the cognizance of the Nuclear Safety Board. CONSUMERS POWER COMPANY BY R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this day of 1983, J: ])/AA jAAj_ v = r er IHERIY l YNll DURFEY Sherry L D fey, Notary Public Notary Jacksen County, Mfeti. Jackson County, Michigan My Commission Expires Nov. 5, IHI My commission expires on 11/5/86. OC0583-0020B-NL02}} | | B. Request for Equivalent Capsule Withdrawal Option The Palisades Reactor Vessel Surveillance Program was designed to monitor radiation induced changes to the mechanical and impact properties of the reactor vessel and consists --of ten capsules containing base metal, weld metal and heat affected zone material representive of the pressure vessel. All of the capsules were inserted into their designated holders prior to the initial reactor startup. |
| | Eight of the capsules are arrayed in two groups 180 degrees apart at the midplane of the core and two capsules are in a low flux region above the core. Each capsule therefore, has a counterpart that is similar in type and quantity of samples located on the opposite side of the reactor core. Core geometry further enhances the similarity of a capsule and its counterpart by producing a neutron flux that is diametrically symmetrical about the circumfrence of the vessel wall. This condition ensures that, at any point in time, a capsule and its counterpart have been exposed to similar, if not OC0583-0020B-NL02 |
| | |
| | L. *_ft 3 |
| | --identical- 0 --neut-ron fluences-and-temperatu-res.- Based--on - - - - - - - - |
| | capsule type, location, content and environmental conditions the following capsules are considered to be essentially equivalent: T-330 & T-150 W-290 & W-110 W-100 & W-280 W-260 & W-80 A-60 & A-240* |
| | Consumers Power Company proposes that Table 4.3.3 (Reactor Vessel Surveillance Coupon Removal Schedule) be modified to provide the option of removing either the primary capsule or its equivalent. Removal of an equivalent capsule will not reduce the effectiveness of the surveillance program and would be used only when difficulty in removing the primary capsule is encountered. The added flexibility of this proposed option would reduce plant outage time and does not violate the requirement of Appendix H of 10 CFR Part SO. |
| | C. Analysis of No Significant Hazards Consideration The Palisades Plant Review Committee has concluded that the proposed changes discussed above do not involve an unreviewed safety question. In addition, the effectiveness of the reactor vessel surveillance program is not reduced and therefore the operation of the facility in accordance with the above proposed changes would not: |
| | : 1. involve a significant increase in the probability or consequences of an accident previously evaluated; or |
| | : 2. create the possibility of a new or different kind of accident from any accident previously evaluated; or |
| | : 3. involve a significant reduction in a margin of safety. |
| | * Equivalent capsule removal provide for in Amendment No 34, January 27, 1978. Capsule A-240 was removed during the second refueling outage. |
| | OC0583-0020B-NL02 |
| | * 4 III._ CONCLUSION -- --------- -----------~ |
| | The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that these changes do not involve an unreviewed safety question and consequently involve no significant hazards considerations. This change has also been reviewed under the cognizance of the Nuclear Safety Board. |
| | CONSUMERS POWER COMPANY BY R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this ~th day of ~ 1983, J: ])/AA=rjAAj_ |
| | v er IHERIY l YNll DURFEY Sherry L D fey, Notary Public Notary Pu~lle, Jacksen County, Mfeti. |
| | Jackson County, Michigan My Commission Expires Nov. 5, IHI My commission expires on 11/5/86. |
| | OC0583-0020B-NL02}} |
|
---|
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
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- ---*tbNSUMERS-POWER COMPANY. * -- _________________;__
DOCKET 50-255 - LICENSE DPR PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS 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. CHANGE(s)
Delete Capsule A-60 from the Reactor Vessel Surveillance Coupon Removal Schedule and change Table 4.3.3, page 4-23 of the Palisades Technical Specifications to read as follows:
Table 4.3.3 Reactor Vessel Surveillance CouEon Removal Schedule 1 2
. Capsule Refueling Capsule Target Removal Time Number Number Location (EFPY @ Refuel No)
Primary Optional A-240 2 Outside Core Barrel 2.26 @ 23 W-290 5 11 Vessel Wall 4.33 @ 5 T-330 5 20 Above Core 4.33 @ 5 W-110 11 5 Vessel Wall 9.21 @ 11 W-100 20 25 Vessel Wall 16.5 @ 20 T-150 20 5 Above Core 16.5 @ 20 W-280 25 20 Vessel Wall 20.6 @ 25 W-260 35 39 Vessel Wall 28.7 @ 35 W-80 39 35 Vessel Wall 32.0 @ 39 1 Refer to Palisades FSAR, Volume 2, Section 4.5.3, Figure 4-11 for illustration of capsule locations 2 EFPY based on 2530 MWt power rating 3 2.26 EFPY from BCL 585-12 Report, March 13, 1979
( 8308100357 830803 i I PDR ADOCK 05000255 l P PDR OC0583-0020B-NL02
L. ',f
- - ---- -- - -- - u-;- -- -nrscuss-roN A. Deletion of Analysis of Capsule A-60 The Palisades surveillance program contained two accelerated capsules (A-60 and A-240) and eight regular capsules.
Capsule A-60 was scheduled to be removed during the second refueling outage, however, problems associated with the upper end fitting precluded removal in the reasonable length of time. Therefore, Capsule A-240, an equivalent capsule, was removed as allowed by Amendment 34 issued January 27, 1978.
The analysis of Capsule A-240 iny~cated that it has been exposed to a fluence of 4.4 x 10 nvt (E lMev) in 2.26 Effective Full Power Years (EFPY) of plant ~~eration. This was substantially greater than the 1.7 x 10 nvt (E lMev) value predicated for the second refueling outage.
As of October 31, 1982, the Palisades reactor has operated for 4.47 EFPY based on a 2530 Mwt poy9r rating and 98,992,680 Mwht accumulated. Assuming 4.4 x 10 nvt (E lMev) in 2.26 EFPY for Capsule A-240, the exposure of 1~apsule A-60 has been calculated to be approximately 8.7 x 10 nvt (E lMev).
This value is significa~§ly greater than the predicted End of Life fluence (3.55 x 10 nvt, E lMev) to the vessel wall, therefore, no useful fracture toughness data would be obtained from the analysis of Capsule A-60. For this reason, Consumers Power Company requests that Capsule A-60 be deleted from the Palisades Reactor Vessel Surveillance Capsule Program.
B. Request for Equivalent Capsule Withdrawal Option The Palisades Reactor Vessel Surveillance Program was designed to monitor radiation induced changes to the mechanical and impact properties of the reactor vessel and consists --of ten capsules containing base metal, weld metal and heat affected zone material representive of the pressure vessel. All of the capsules were inserted into their designated holders prior to the initial reactor startup.
Eight of the capsules are arrayed in two groups 180 degrees apart at the midplane of the core and two capsules are in a low flux region above the core. Each capsule therefore, has a counterpart that is similar in type and quantity of samples located on the opposite side of the reactor core. Core geometry further enhances the similarity of a capsule and its counterpart by producing a neutron flux that is diametrically symmetrical about the circumfrence of the vessel wall. This condition ensures that, at any point in time, a capsule and its counterpart have been exposed to similar, if not OC0583-0020B-NL02
L. *_ft 3
--identical- 0 --neut-ron fluences-and-temperatu-res.- Based--on - - - - - - - -
capsule type, location, content and environmental conditions the following capsules are considered to be essentially equivalent: T-330 & T-150 W-290 & W-110 W-100 & W-280 W-260 & W-80 A-60 & A-240*
Consumers Power Company proposes that Table 4.3.3 (Reactor Vessel Surveillance Coupon Removal Schedule) be modified to provide the option of removing either the primary capsule or its equivalent. Removal of an equivalent capsule will not reduce the effectiveness of the surveillance program and would be used only when difficulty in removing the primary capsule is encountered. The added flexibility of this proposed option would reduce plant outage time and does not violate the requirement of Appendix H of 10 CFR Part SO.
C. Analysis of No Significant Hazards Consideration The Palisades Plant Review Committee has concluded that the proposed changes discussed above do not involve an unreviewed safety question. In addition, the effectiveness of the reactor vessel surveillance program is not reduced and therefore the operation of the facility in accordance with the above proposed changes would not:
- 1. involve a significant increase in the probability or consequences of an accident previously evaluated; or
- 2. create the possibility of a new or different kind of accident from any accident previously evaluated; or
- 3. involve a significant reduction in a margin of safety.
- Equivalent capsule removal provide for in Amendment No 34, January 27, 1978. Capsule A-240 was removed during the second refueling outage.
OC0583-0020B-NL02
- 4 III._ CONCLUSION -- --------- -----------~
The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that these changes do not involve an unreviewed safety question and consequently involve no significant hazards considerations. This change has also been reviewed under the cognizance of the Nuclear Safety Board.
CONSUMERS POWER COMPANY BY R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this ~th day of ~ 1983, J: ])/AA=rjAAj_
v er IHERIY l YNll DURFEY Sherry L D fey, Notary Public Notary Pu~lle, Jacksen County, Mfeti.
Jackson County, Michigan My Commission Expires Nov. 5, IHI My commission expires on 11/5/86.
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