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Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[Table view] Category:Technical Specification
MONTHYEARPNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML22102A2482022-04-14014 April 2022 Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML21152A1112021-06-0101 June 2021 Proposed Changes (mark-up) to Palisades Plant - Appendix a Technical Specifications, and Appendix B Environmental Protection Plan Pages ML21152A1132021-06-0101 June 2021 Palisade Nuclear Plant - Proposed Technical Specifications Bases Changes RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls PNP 2019-017, Submittal of Changes to Technical Specifications Bases2019-03-21021 March 2019 Submittal of Changes to Technical Specifications Bases PNP 2018-052, Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force.2018-11-16016 November 2018 Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force. ML18270A3222018-09-27027 September 2018 Attachment 1: Description and Evaluation of Technical Specifications Changes ML18270A3242018-09-27027 September 2018 Attachment 3: Proposed Changes and Appendix a Technical Specifications Pages ML18270A3252018-09-27027 September 2018 Attachment 4: Page Change Instructions and Revised Pages, and Appendix a Technical Specifications ML18270A3262018-09-27027 September 2018 Attachment 5: Proposed Technical Specification Bases Changes PNP 2017-067, Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases2017-11-0808 November 2017 Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases PNP 2016-046, License Amendment Request for Editorial and Administrative Changes to Technical Specifications2016-11-0909 November 2016 License Amendment Request for Editorial and Administrative Changes to Technical Specifications PNP 2014-088, Report to NRC of Changes to Technical Specifications Bases2014-09-15015 September 2014 Report to NRC of Changes to Technical Specifications Bases PNP 2014-042, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c, Using the Consolidated Line Item Improvement Process2014-06-11011 June 2014 License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c, Using the Consolidated Line Item Improvement Process PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases2012-11-0909 November 2012 Report to NRC of Changes to Technical Specifications Bases PNP 2011-032, Report to NRC of Changes of Technical Specifications Bases2011-04-25025 April 2011 Report to NRC of Changes of Technical Specifications Bases PNP 2011-018, Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years2011-04-0606 April 2011 Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years ML1020105792010-07-20020 July 2010 License Amendment Request for Emergency Diesel Generator Fuel Oil and Lube Oil Systems ML0930604142009-11-0202 November 2009 Report of Changes to Technical Specifications Bases ML0913501812009-05-14014 May 2009 Supplement to License Amendment Request: Changes to Technical Specification Administrative Controls Section ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions ML0901602382009-02-0606 February 2009 Issuance of Amendment Spent Fuel Pool Region I Storage Requirements ML0827404452008-11-20020 November 2008 Issuance of Amendment Eliminate License Condition 2.F ML0822703122008-08-14014 August 2008 Report of Changes to Technical Specifications Bases ML0723203952007-08-16016 August 2007 Report of Changes to Technical Specifications Bases ML0722201032007-07-25025 July 2007 Submittal of Technical Specifications Bases Changes ML0718002162007-06-28028 June 2007 License Amendment Request: Replacement of Containment Sump Buffer ML0714501052007-05-31031 May 2007 Technical Specifications Pages Re Programs and Manuals for Steam Generator ML0631803592006-11-0606 November 2006 License Amendment Request: Realistic Large Break Loss-of-Coolant Accident ML0628303852006-09-25025 September 2006 Alternative Source Term- Proposed License Amendment ML0623000332006-08-17017 August 2006 Report of Changes to Technical Specifications Bases ML0524102132005-08-22022 August 2005 Report of Changes to Technical Specifications Bases ML0425904452004-09-0202 September 2004 Report of Changes to Technical Specifications Bases ML0421604082004-08-0202 August 2004 Tech Spec Pages for Amendment No. 217 Regarding the Relocating of the Primary Coolant System Pressure, Cold-Leg Temperature and Flow Departure from Nucleate Boiling Limits to the Core Operating Limits Report ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0330001112003-10-17017 October 2003 Report of Changes to Technical Specifications Bases ML0328900502003-10-0606 October 2003 License Amendment Request: Increase Rated Thermal Power, Response to Request for Additional Information ML0316110532003-06-0303 June 2003 License Amendment Request: Increase Rated Thermal Power ML0303805792003-01-22022 January 2003 Technical Specifications and Bases ML0231701012002-10-31031 October 2002 Report of Changes to Technical Specifications Bases ML0207201012002-03-0101 March 2002 License Amendment Request, Surveillance Requirement Frequency for Containment Spray Nozzle Inspections ML0205901512002-02-26026 February 2002 Amendment No. 207 Retechnical Specification on Spent Fuel Pool Boron Concentration ML18344A3791978-06-15015 June 1978 Proposed Technical Specification Changes on Power Distribution Limits ML18353B1461978-03-0909 March 1978 Iodine Removal System - Proposed Technical Specification Changes ML18353A8671978-02-22022 February 1978 Letter Proposed Technical Specifications Change on Heatup and Cooldown Curves for Cycle 3 Operation ML18353A8741978-02-21021 February 1978 Letter Proposed Technical Specifications Change on Steam Generator Operating Allowance ML18347A1881978-01-0303 January 1978 Proposed Technical Specifications Changes Relating to Overpressure Protection System ML18353B1451977-11-11011 November 1977 Transmittal of Technical Specification - Deletion of Annual Operating Report ML18353B1471977-11-10010 November 1977 Proposed Technical Specification Changes for Steam Generator Inservice Inspection 2023-12-14
[Table view] Category:Amendment
MONTHYEARPNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML22102A2482022-04-14014 April 2022 Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML21152A1112021-06-0101 June 2021 Proposed Changes (mark-up) to Palisades Plant - Appendix a Technical Specifications, and Appendix B Environmental Protection Plan Pages RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls PNP 2018-052, Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force.2018-11-16016 November 2018 Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force. PNP 2011-018, Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years2011-04-0606 April 2011 Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions ML0901602382009-02-0606 February 2009 Issuance of Amendment Spent Fuel Pool Region I Storage Requirements ML0827404452008-11-20020 November 2008 Issuance of Amendment Eliminate License Condition 2.F ML0718002162007-06-28028 June 2007 License Amendment Request: Replacement of Containment Sump Buffer ML0714501052007-05-31031 May 2007 Technical Specifications Pages Re Programs and Manuals for Steam Generator ML0631803592006-11-0606 November 2006 License Amendment Request: Realistic Large Break Loss-of-Coolant Accident ML0628303852006-09-25025 September 2006 Alternative Source Term- Proposed License Amendment ML0421604082004-08-0202 August 2004 Tech Spec Pages for Amendment No. 217 Regarding the Relocating of the Primary Coolant System Pressure, Cold-Leg Temperature and Flow Departure from Nucleate Boiling Limits to the Core Operating Limits Report ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0328900502003-10-0606 October 2003 License Amendment Request: Increase Rated Thermal Power, Response to Request for Additional Information ML0316110532003-06-0303 June 2003 License Amendment Request: Increase Rated Thermal Power ML0205901512002-02-26026 February 2002 Amendment No. 207 Retechnical Specification on Spent Fuel Pool Boron Concentration ML18344A3791978-06-15015 June 1978 Proposed Technical Specification Changes on Power Distribution Limits ML18347A1881978-01-0303 January 1978 Proposed Technical Specifications Changes Relating to Overpressure Protection System ML18353B1471977-11-10010 November 1977 Proposed Technical Specification Changes for Steam Generator Inservice Inspection ML18347A1711977-09-26026 September 1977 Additional Information Relating to Power Increase Request ML18348A7651976-11-16016 November 1976 Proposed Change to Technical Specification to Modify Spent Fuel Storage Facility ML18347A5511976-10-0808 October 1976 Transmitting Proposed Change to Tech Spec Concerning Operability & Surveillance Requirements for Hydraulic Shock Suppressors ML18347A6601976-06-0909 June 1976 Re Cpc'S 5/25/1976 Event Report, Requesting Change to Tech Spec to Operation of Diesel Generator with One High-Pressure Safety Injection Pump Out of Service ML18348A7701976-03-12012 March 1976 Proposed Change to Technical Specification to Modify Requirements for Testing of Primary System Pump Combinations & for Load Testing of Diesel Generators ML18348A7751976-02-25025 February 1976 Proposed Change to Technical Specification to Delete Requirement for Operation of Fuel Pool Charcoal Adsorber After I-131 Level in Irradiated Fuel Has Decayed by Factor of 10 ML18348A7761976-01-30030 January 1976 Proposed Change to Technical Specification to Generalize Tech Spec to Allow for Reactor Refueling Without Requiring Additional Tech Spec Changes ML18348A7801976-01-30030 January 1976 Proposed Change to Technical Specification to Revise Steam Generator Tube Plugging Criteria ML18348A7861975-03-10010 March 1975 Proposed Change to Technical Specification Based on Eddy-Current Inspection of Steam Generator 2023-12-14
[Table view] |
Text
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Power company General Offices: 212 west Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 January 30, 1976
'Director of Nuclear Reactor Regulation Att: Mr Robert A. Purple, chief Operating Reactor Branch No 1 US Nuclear Regulatory Commission Washington, DC 20555 DOCKEI' 50-255, LICENSE DPR-~O PALISADES PLANT - PROPOSED TECHNICAL SPECIFICATIONS CHANGE - PALISADES CYCLE 2 RELOAD FUEL By letters dated December 15, 1975 and December 29, 1975, we transmitted copies of reports containing information on Palisades Batch D and E reload fuel, re-spectively.
- As discussed previously with members of your staff, additional information con~
cerning the Palisades reactor refueling would be transmitted. This information includes a proposed Technical Specifications change (attached) and art analysis entitled, "Palisades LOCA Analyses Using the ENC WREM-Base PWR ECCS Evaluation Model" (No XN-76-4 dated January 1976), which discusses the ECCS analysis as-sociated with six postulated pipe break accidents. This analysis is being pro-vided under separate cover.
Additional information on analysis associated with the Palisades Cycle 2 refuel-ing will be transmitted about February 10, 1976 (plant transients) and February 20, 1976 (additional ECCS analysis).
The changes proposed in this request are primarily designed to generalize the present Technical Specifications to allow for reactor refueling without requiring additional Technical Specifications changes.
In addition to the proposed Technical Specifications changes, it should be noted that the ECCS model being used for the analysis is different from that previously used, that fuel from a different manufacturer (Exxon Nuclear Corporation - ENC) is being analyzed for the reload core, and that ENC will. be conducting the analy-sis both for the fuel supplied by ENC and for that _ ...,._ r.~iously_by-o.theFs-.- --*----
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David A. Bixel 6
- Assistant Nuclear Licensing Administrator CC: JGKeppler, USNRC File
- 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 Speci-fications contained in Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October l6, 1972, be changed as described in Sec-tion I below.
I. Changes A. Change Section 5.3.2 (a) as follows:
"a. The reactor core shall approximate a right circular cylinder with an equivalent diameter of about 136 inches and an active height of about 132 inches."
B. Change Section 5.3.2 (b) as follows:
- "b. The reactor core shall consist of approximately 43,000 Zircaloy-4 clad fuel rods containing slightly enriched uranium in the form of sintered uo 2 pellets. The fuel rods shall be grouped into 204 assemblies.
A core plug or plugs may be used to replace one or more fuel assemblies subject to the analysis of the resulting power distribution."
C. Change Section 5.3.2 (c) as follows:
"c. The fully loaded core shall contain approximately 211,000 pounds uo 2 and approximately 56,000 pounds of Zircaloy-4. Poison may be placed in the fuel bundles for long-term reactivity control. "
D. Delete Item 1 of Appendix c. (Requirements deleted or incorporated in Appendix A. )
E. Change Section 3.1.1 (b) by adding the following at the end of the para-graph:
"Four primary coolant pumps shall be in operation whenever the reactor is operated continually above 5%, of rated power (exception to _!_1!_~-~--~P~~:i~-- _____ _
______ fication-i-s-permit-ted-as*-describe-d-in-Tao1ez:-3-~r;-rtem-iT.-11--
_F. Change Section 3.1.1 (c) to read as follows:
"c. The minimum flow for various power levels shall be as shown in Table 2.3.1. The measured "Four Primary Coolant Pumps Operating" reactor coolant vessel flow (as determined by reactor coolant pumps differential pressure and pump perfonnance curves) shall be 127 .8 lb/h or greater."
1
- G. Change the basis to Section 3.1.l by adding the following paragraph:
"The thermal margin and ECCS anazysis conducted for the reactor core assume a vessel flow of 124 x 106 lb/h. The value is consistent with a measured fl.ow of 127.8 x 106 lb/hand an uncertainty of 3% (subtract from the measured flow) * "
H. Change Table 2.3.1, Item 1, for two and three primary coolant pumps op-erating as follows:
Three Primary Coolant Two Primary Coolant Pumps Operating Pumps Operating "25% of rated power ( 4 )" "5% of rated power ( 4 )"
(Continuous operation (Continuous operation not permitted. ) not permitted.)
4
( )0peration with two or three pumps is permitted only to provide for an orderly shutdown (or start-up) and to provide for the conduct of reactor internals, noise monitoring test measurements (a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of operation each time this test is* conducted).
I. Delete Appendix B Items 1, 2, 3, 5 and 6. (These requirements are pro-posed to be incorporated elsewhere or are no longer applicable.)
J. Change proposed Section 3.18.1 (proposed in July 9, 1975 submittal) to read as follows :
I "3.18.1 The linear heat generation rate with appropriate consideration of normal flux peaking, measurement-calculational uncertainty, engineer-ing factor, increase in linear heat rate due to axial fuel densification, .
power measurement uncertainty, and flux peaking augmentation, shall not exceed that limit which causes calculated ECCS performance, as predicted by an evaluation model approved by the NRC as satisfying the requirements of 10 CFR 50, Appendix K, to exceed the "Acceptance Criteria for Emergency Core Cooling System for Light Water Cooled Nuclear Power Reactors" as given in 10 CFR 50.46(b).
"Unless otherwise justified, the measure;ment-calculational uncertainty shall be 10%, the engineering factor shall be 3%, the increase in linear heat rate due to axial densification shall be 1.75% (as applied to hot dimensions), the power measurement uncertainty shall be 2%, and the flux peaking augmentation factor shall be as given in Figure 3-6 for uncol-lapsed fuel and Figure 3-7 for collapsed fuel. Augmentation factors for pressurized densifi_~ation~r_esistant-ENC-fuel-and-pressurizm--:nign-d.ensity___ _
-cE-fuersnaIT1>eI~o."
- ~is Technical Specifications request assumes that the changes proposed on July 9, 1975 (re-evaluation of ECCS cooling performance) a~e accepted prior 2
- to or as a part of this proposed change.
item is given below.
A.
A discussion of the individual This proposed change generalizes the reactor core design with respect to equivalent diameter and heights. This change makes the Technical Speci-fications consistent with planned reload fuel design which may utilize slightly different fuel assembly design parameter (see Table 4.1 of our December 29, 1975 submittal, "Palisades Cycle 2 Reload Fuel Licensing Data Submittal").
B&C. This proposed change deletes specific core fuel loading requirements.
These.requirements are effectively controlled in Section 3 of the Tech-nical Specifications.
D. This change deletes the present temporary thermal power restriction and allows the plant to return to its rated power level of 2200 MWt. This power level is used in our ECCS evaluations submitted as part of the Palisades Cycle 2 Reload Fuel Licensing Data Submittal.
Other parts of this appendix (Appendix C) are incorporated into Appen-dix A. See items E, F, and G.
E&H. These changes delete the option of continuous operation with less than four primary coolant pumps in operation. Limited operation with two and three pumps is permitted to effect an orderly shutdown or start-up of the plant and to provide for "noise monitoring" to test for core internals vibration.
These added restrictions to the present Technical Specificatio~s are considered temporary and are expected to be removed following completion of an analysis justifying operation with less than four coolant pumps.
F&G. This change adds a minimum flow to the Appendix A Technical Specifications.
This flow is consistent with that used in the Core 2 ECCS and thermal margin analysis.
I. Many items in Appendix B are deleted. These items are no longer applicable or are incorporated elsewhere as follows:
- 1. Item 1 - Rated power is defined in Section 1.1.
- 2. Item 2 Steam generator leakage requirements are proposed in changes associated with our steam generator tube plugging criteria request.
- 3. Item 3 - This __Eiect_ion__ is_no_longer-appl-icab:le-since--core- ournup ex-------
- - - --------------ceeds-1o-;2b-5MWd/Ml'V. -
- 4. Item 5 - A thermal power limit for unpressurized fuel is being deter-mined as part of the analysis being conducted for the core reload *
- 5. Item 6 - Data logger operability is considered in the proposed Tech-nical Specifications of July 9, 1975.
3
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- J. This change modifies our proposed change of July 9, 1975 transmitted as part of the re-evaluation of ECCS cooling performance. The change in-corporates consideration of pressurized, densification resistant fuel and recognizes that certain calculational uncertainties may change due to different fuel manufacturing considerations, etc.
III. Conclusion This change has not been reviewed by our Palisades Plant Review Committee or the Safety and Audit Review Board. These reviews will be conducted as information becomes available and we will advise you should ariy of the proposed changes be deemed inappropriate.
CONSUMERS POWER COMPANY Sworn and sub-scribed to before me this 30th day of January 1976.
Jackson County, Michigan MY' commission expires May 18, 1976 *
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