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| | consumers Power company General Offices: 212 West Michigan Avenue, .Jackson, Michigan 49201 |
| * consumers Power company General Offices: 212 West Michigan Avenue, .Jackson, Michigan 49201
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| * Area Code 517 788-0550 Jrme 28, 1976 Mr James G. Keppler US Nuclear Regulatory Commissi 799 Roosevelt Road Mail Soction Dockel Clark Glen Ellyn, IL 60137 DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT On June 15, 1976, Mr G. Hein of the Palisades Plant staff reported to Mr K. | | * Area Code 517 788-0550 Jrme 28, 1976 Mr James G. Keppler US Nuclear Regulatory Commissi 799 Roosevelt Road Mail Soction Dockel Clark Glen Ellyn, IL 60137 DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT On June 15, 1976, Mr G. Hein of the Palisades Plant staff reported to Mr K. |
| Baker of your office that we were evaluating a question that had arisen* and considered that it might be reportable under Technical Specification Section | | Baker of your office that we were evaluating a question that had arisen* and considered that it might be reportable under Technical Specification Section |
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| Ralph B. Sewell (Signed) | | Ralph B. Sewell (Signed) |
| . Ralph B. Sewell Nuclear Licensing Administrator | | . Ralph B. Sewell Nuclear Licensing Administrator |
| * T.o Palisades Pla ~ew Committee
| | |
| | T.o Palisades Pla ~ew Committee |
| ' ' /112./) | | ' ' /112./) |
| RBSewell, P-21-317 /':::'f/~ | | RBSewell, P-21-317 /':::'f/~ |
| * FROM DATE June 25, 1976 SUBJECT REVIEW OF EFF:i;;CTS OF A SEICHE INTERNAL
| | FROM DATE June 25, 1976 SUBJECT REVIEW OF EFF:i;;CTS OF A SEICHE INTERNAL |
| .CORRESPONDENCE BLHarshe, Covert cc DABixel, P-21-319 HWKeiser, P-21-109 I have reviewed. the following documentation with respect to how seiches were considered in evnluation of the Plant Design: | | .CORRESPONDENCE BLHarshe, Covert cc DABixel, P-21-319 HWKeiser, P-21-109 I have reviewed. the following documentation with respect to how seiches were considered in evnluation of the Plant Design: |
| : 1) The references listed in DABixel's letter of ~my 27, 1976, to JGLewis/PRC. | | : 1) The references listed in DABixel's letter of ~my 27, 1976, to JGLewis/PRC. |
| : 2) Event Report PAL-76-020. | | : 2) Event Report PAL-76-020. |
| : 3) HHKeiser letter of June 21, 1976, to ?RC. | | : 3) HHKeiser letter of June 21, 1976, to ?RC. |
| I hnve concluded that the potential loss of four Primary Coolant PUmps due to flooding caused by a seiche is not an unreviewed safety question. In the | | I hnve concluded that the potential loss of four Primary Coolant PUmps due to flooding caused by a seiche is not an unreviewed safety question. In the follm'ling paragraphs I will attempt to o*ntline the basis for my conclusion |
| * follm'ling paragraphs I will attempt to o*ntline the basis for my conclusion
| |
| * First, the Loss of Coolant Flow Incident described in Section 14.7 is an !lntici- | | * First, the Loss of Coolant Flow Incident described in Section 14.7 is an !lntici- |
| :pated transient. An anticipated transie::-it is sonething that is expected to occur several tir:1es or r:iore during plant life. ?or anticipated transients a m.inir::urn trar1sient D~rn ratio limit of 1. 30 has generally been estcrblished by the HRC as the acceptance criteria. This limit i9 established to insure that damage to the fuel will not occur for these moderate probability events. I note *specificall~r that a sfr:ultaneous loss of four coolant pumps was not* | | :pated transient. An anticipated transie::-it is sonething that is expected to occur several tir:1es or r:iore during plant life. ?or anticipated transients a m.inir::urn trar1sient D~rn ratio limit of 1. 30 has generally been estcrblished by the HRC as the acceptance criteria. This limit i9 established to insure that damage to the fuel will not occur for these moderate probability events. I note *specificall~r that a sfr:ultaneous loss of four coolant pumps was not* |
| considered in this tran'sient analysis because it was judged to be of very low probability. Section 14.7.4 of the FSAR states in part: ":!!'or the case of a single stuck rotor there will be some rods for which the transien*t; mrn ratio droJ:ls below 1.30.however the very low probability of this incident allows acceptance of this.condition."* That statement also applies p'.1ilosophicnlly to the very low probability case of a s:i.:r.ml taneous loss of all four primi:..ry coolant pumps. | | considered in this tran'sient analysis because it was judged to be of very low probability. Section 14.7.4 of the FSAR states in part: ":!!'or the case of a single stuck rotor there will be some rods for which the transien*t; mrn ratio droJ:ls below 1.30.however the very low probability of this incident allows acceptance of this.condition."* That statement also applies p'.1ilosophicnlly to the very low probability case of a s:i.:r.ml taneous loss of all four primi:..ry coolant pumps. |
| FSAR Ap:pendix A.2(g) describes the Plant design with respect to flooding as protected up to elevation 590 feet. This provides a margin of 7.3 feet above the highest reported nodern lake level. Six (6) of these 7 .3 feet are described as. an allowance* for seiche, thus, I would conclude that the J?ossibility of a seiche was properly considered in the design of the Plant against f'looding to the 590 foot level. I note that the bottom of the four primary coolant pwnp breakers are mou.~ted at the 590 foot level * | | FSAR Ap:pendix A.2(g) describes the Plant design with respect to flooding as protected up to elevation 590 feet. This provides a margin of 7.3 feet above the highest reported nodern lake level. Six (6) of these 7 .3 feet are described as. an allowance* for seiche, thus, I would conclude that the J?ossibility of a seiche was properly considered in the design of the Plant against f'looding to the 590 foot level. I note that the bottom of the four primary coolant pwnp breakers are mou.~ted at the 590 foot level * |
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| A rev.i.ew of question 2 .4 of Amendments 15 and 18 to the FSAR reveals the | | A rev.i.ew of question 2 .4 of Amendments 15 and 18 to the FSAR reveals the following key words. They are: |
| * following key words. They are:
| |
| "Maximum increase" "especially severe seiche" * | | "Maximum increase" "especially severe seiche" * |
| "shutdown safely" "with or without s:pecial procedures and provisions executed at the time of flooding." | | "shutdown safely" "with or without s:pecial procedures and provisions executed at the time of flooding." |
| The context of this question is an inextremis situation. It is -intended to convey a very low probability event and asks what the maximum flooding level is that equipment reg_uired to obtain and maintain a safe shutdo~*m condition would be functional. The answer given was 594 feet 8 inches and states that equipment required to obtain and maintain a safe shutdown*condition would not be flooded until water level exceeded thi.s value. This question did not intend to imply that the four primary coolant pu.mps could not trip sequentially *. The probability.is conveyed as extremely low as compared to anticipated transients. | | The context of this question is an inextremis situation. It is -intended to convey a very low probability event and asks what the maximum flooding level is that equipment reg_uired to obtain and maintain a safe shutdo~*m condition would be functional. The answer given was 594 feet 8 inches and states that equipment required to obtain and maintain a safe shutdown*condition would not be flooded until water level exceeded thi.s value. This question did not intend to imply that the four primary coolant pu.mps could not trip sequentially *. The probability.is conveyed as extremely low as compared to anticipated transients. |
| The six foot allowance for a seiche appears conservative. Section 2.2.2(a) shows the greatest level change due to a seiche over an 105 year period to be 6 feet at Michi"g!?.n City, Indiana and 0 at the same time at Holland, J:ld.chigan. | | The six foot allowance for a seiche appears conservative. Section 2.2.2(a) shows the greatest level change due to a seiche over an 105 year period to be 6 feet at Michi"g!?.n City, Indiana and 0 at the same time at Holland, J:ld.chigan. |
| Further, J~IT(eiser's calculations show the maximum level .at Palisades to be | | Further, J~IT(eiser's calculations show the maximum level .at Palisades to be much less than 6 ~eet |
| * much less than 6 ~eet
| |
| * Therefore, I have concluded that the FSAR has appropriately considered and evaluated the effects _of seiches on the Palisades Plant and the design and construction of the Palisades Plant was in accordance with the requirements of the FSAR. Thus, my conclusion is that this item is not an unreviewed safety qu:-;!stion and is not reportable in accordance with Section 6. 9.2 a-8 of the Technical Specifications. Further, I believe that this event report should be closed out. With PRC concurrence, I will inform the NRC that we no longer consider this event reportable and are therefore canceling it * | | * Therefore, I have concluded that the FSAR has appropriately considered and evaluated the effects _of seiches on the Palisades Plant and the design and construction of the Palisades Plant was in accordance with the requirements of the FSAR. Thus, my conclusion is that this item is not an unreviewed safety qu:-;!stion and is not reportable in accordance with Section 6. 9.2 a-8 of the Technical Specifications. Further, I believe that this event report should be closed out. With PRC concurrence, I will inform the NRC that we no longer consider this event reportable and are therefore canceling it * |
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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:Memoranda
MONTHYEARML23297A0532023-11-27027 November 2023 Restart Panel Charter ML20231A2202020-08-17017 August 2020 Summary of Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of the Palisades Nuclear Plant ML16182A5142016-06-30030 June 2016 Summary of the June 23, 2016, Public Meeting Regarding Palisades Nuclear Plant ML16138A1812016-05-16016 May 2016 EA-15-039 Palisades Federal Register Memo and Order ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML15127A5692015-05-0707 May 2015 Final Task Interface Agreement-Regulatory Position on Design Life of Safety-Related Structures, Systems, & Components Related to Unresolved Items at D. C. Cook, Monticello, & Palisades (TIA 2014-01) ML15054A3962015-04-0606 April 2015 Federal Register Notice on Final Director'S Decision on 10 CFR 2.206 Petition from Mr. Michael Mulligan at Palisades Nuclear Plant ML13261A2282013-09-23023 September 2013 Notice of Forthcoming Conference Call with Entergy Nuclear Operations, Inc., on Palisades Equivalent Margins Analysis ML13042A2932013-02-11011 February 2013 Meeting Summary with NRC to Discuss Nrc'S Perspectives on Leaks, and the Regulatory Requirements That Apply on the Repair of Such Leaks ML12305A4512012-12-0101 December 2012 Branch Chief Reassignment ML12306A3672012-11-0808 November 2012 Approval Memo Palisades Request for Deviation to the Reactor Oversight Process Action Matrix ML12305A5472012-11-0101 November 2012 Pre-application Meeting Notice Palisades ME9852 ML1115704052011-06-0606 June 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Implementation of Quality Oversight and Verification Programs at Entergy Sites Including Actions Being Taken to Enhance Effectiveness ML1111107222011-05-0303 May 2011 Final Response to TIA 2011-006, Palisades Nuclear Plant Reactor Vessel Bare Metal Head Exam - Compliance with Code Case N-729-1 ML1107504052011-03-21021 March 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Fleetwide Submittal for Proposed Technical Specification and Quality Assurance Program Manual Changes Related to Unit Staff Qualification Requirements ML1012601282010-06-29029 June 2010 TIA Response ML1015506112010-06-0909 June 2010 Notice of Pre-Application Meeting with Entergy Nuclear Operations Inc. to Discuss Pressurized Thermal Shock Analysis ML1011604932010-04-27027 April 2010 05/12-13/2010 Notice of Meeting with Energy Nuclear Operations LLC (ENO) Regarding Response to Generic Letter 2004-02 for Palisades Nuclear Plant ML1002101862010-01-20020 January 2010 Memo to Christine. A. Lipa Response to Region III Technical Assistance Request-Palisades Plant Multi-Assembly Sealed Basket No. 4 (Msb #4) - Weld Flaw Analysis ML0927301372009-10-0909 October 2009 Safety Evaluation by the Office of Nuclear Reactor Regulation Corporate Restructuring Conversion of Companies and Stock Split-Off by Entergy Nuclear Operations, Inc and Subsidiaries ML0925400322009-09-17017 September 2009 Final Task Interface Agreement - Re-Evaluation of Implementation of Limiting Condition for Operation 3.0.4a, Mode Change Limitations, at Palisades Nuclear Plant (TIA2009-005) ML0912504972009-05-15015 May 2009 Summary of Telephone Conference Call Held on April 23, 2009, Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc. Regarding Progress on National Fire Protection Association (NFPA) Standard 805 Transition Activities ML0909601482009-04-17017 April 2009 (Pnp) - Summary of Telephone Conference Call Held on March 17, 2009, Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc. Regarding Progress on National Fire Protection Association (NFPA) Standard 805 ... ML0905507692009-02-25025 February 2009 Notice of Pre-Application Meeting with Palisades to Discuss Spent Fuel Criticality Amendment for Palisades Nuclear Plant ML0835902692008-12-17017 December 2008 Memo 12/17/2008 Re 2006 Palisades Proposed Examination Not Available in ADAMS ML0831908362008-12-15015 December 2008 Summary of Telephone Conference Call Held on November 3, 2008, Between the NRC and Entergy Operations, Inc. Concerning Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10 CFR 50.48(C), Nat ML0833604952008-12-11011 December 2008 LIC-109 Acceptance Review for License Amendment Request for Spent Fuel Pool Region I Criticality for Palisades ML0834301532008-12-0404 December 2008 Canceled - 12/16/2008 Meeting Notice, Meeting with Entergy Nuclear Operations, Inc. (Eno), Palisades Nuclear Plant ML0823503502008-08-20020 August 2008 Memo to Christine Lipa Request for Additional Information; Region III TAR Requesting Assessment of Palisades Weld Flaw Analysis for Loaded Spend Fuel Cask Msb No. 4 (TAC A10126) ML0813000962008-05-0909 May 2008 TIA Regarding LCO 3.0.4a ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0708805192007-04-0909 April 2007 Memo J Cameron, Request for Additional Information, Region III, TAR Requesting Assessment of Palisades Weld Flaw Analysis for Loaded Spent Fuel Cask Msb No. 4, TAC No. A10126 (Dsfst 20070005) ML0707207672007-03-20020 March 2007 Encl 1 - Staff'S Response to Petitioner'S Comments to 03/20/07 - Ltr T Lodge, Counsel for Petitioners, Issuance of Director'S Decision DD-07-02 Under 10 CFR 2.206 - Palisades Nuclear Plant, Docket Nos. 72-7, 50-255 ML0706101422007-03-0909 March 2007 February 2007 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations (10 Cfr), Section 2.206 ML0704001932007-02-22022 February 2007 Response Memo to Task Interface Agreement 2006-004 ML0701001592007-01-29029 January 2007 December 2006 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 ML0700402152007-01-22022 January 2007 Safety Evaluation by the Office of Nuclear Reactor Regulation Re Direct Transfer of Licenses from Consumers Energy Company to Entergy Nuclear Palisades, LLC and Entergy Nuclear Operations, Inc ML0635404462007-01-11011 January 2007 Memo to Commission Fm Reyes Renewal of Full-Power Operating License for the Palisades Nuclear Plant ML0634502502006-12-19019 December 2006 November 2006 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 ML0617805592006-07-10010 July 2006 Revised Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. ML0618102812006-06-29029 June 2006 Memo 06/29/06 Palisades DRS Input to DRP IR 06-004 ML0607401012006-03-14014 March 2006 04/05/06 - Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement (Dseis) for License Renewal at Palisades Nuclear Plant (Palisades) ML0602502942006-01-25025 January 2006 Canceled Notice of Meeting with Nuclear Management Company Regarding Fleet Transition to NFPA Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants ML0601800802006-01-18018 January 2006 Notice of Forthcoming Meeting with Palisades Nuclear Plant and Nuclear Management Company (NMC) to Discuss Removing Trisodium Phosphate from the Containment at Palisades Nuclear Plant for One Cycle ML0611102682005-11-0707 November 2005 Memorandum to Marc Dapas, Riii from Edwin Hacket, NRR Re Response to Task Interface Agreement 2005-06, Regarding Licensing Basis for, and Seismic Design of, the Palisades Independent Spent Fuel Storage Installation (ISFSI) ML0530404252005-10-28028 October 2005 Summary of Telephone Conference Call Held on September 7, 2005, Between the U.S. Nuclear Regulatory Commission (NRC) and Nuclear Management Company, LLC, Concerning Draft Request for Additional Information Pertaining to the Palisades Nuclea ML0520805482005-07-27027 July 2005 Forthcoming Exit Meeting with Nuclear Management Company to Present Results of the Palisades Nuclear Plant Aging Management Program and Aging Management Review Audits ML0611102662005-05-12012 May 2005 Memorandum to James Lyons, NRR, from Marc Dapas, Riii Re Request for Technical Assistance-Licensing Basis for, and Seismic Design of, the Palisades Independent Spent Fuel Storage Installation (ISFSI) Supplemental Information ML0511203112005-05-11011 May 2005 Transmittal of Summaries of Final ASP Analyses 2023-11-27
[Table view] |
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consumers Power company General Offices: 212 West Michigan Avenue, .Jackson, Michigan 49201
- Area Code 517 788-0550 Jrme 28, 1976 Mr James G. Keppler US Nuclear Regulatory Commissi 799 Roosevelt Road Mail Soction Dockel Clark Glen Ellyn, IL 60137 DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT On June 15, 1976, Mr G. Hein of the Palisades Plant staff reported to Mr K.
Baker of your office that we were evaluating a question that had arisen* and considered that it might be reportable under Technical Specification Section
- 6.9.2.a-8. The question involved the postulated loss of four primary coolant pumps due to flooding caused by a postulated seiche. This was classified as Event Report No 76-020.
After further review, we have concluded that the effects of seiches were appropriately considered in the design a.nd. construction of the Palisades Plant. Thus,~.:we are no longer considering this item reportable and. are, therefore, cancelling it. Some of the reason*s f'or this conclusion are sum-marized in the attached. lett.er.
Ralph B. Sewell (Signed)
. Ralph B. Sewell Nuclear Licensing Administrator
T.o Palisades Pla ~ew Committee
' ' /112./)
RBSewell, P-21-317 /':::'f/~
FROM DATE June 25, 1976 SUBJECT REVIEW OF EFF:i;;CTS OF A SEICHE INTERNAL
.CORRESPONDENCE BLHarshe, Covert cc DABixel, P-21-319 HWKeiser, P-21-109 I have reviewed. the following documentation with respect to how seiches were considered in evnluation of the Plant Design:
- 1) The references listed in DABixel's letter of ~my 27, 1976, to JGLewis/PRC.
- 2) Event Report PAL-76-020.
- 3) HHKeiser letter of June 21, 1976, to ?RC.
I hnve concluded that the potential loss of four Primary Coolant PUmps due to flooding caused by a seiche is not an unreviewed safety question. In the follm'ling paragraphs I will attempt to o*ntline the basis for my conclusion
- First, the Loss of Coolant Flow Incident described in Section 14.7 is an !lntici-
- pated transient. An anticipated transie::-it is sonething that is expected to occur several tir:1es or r:iore during plant life. ?or anticipated transients a m.inir::urn trar1sient D~rn ratio limit of 1. 30 has generally been estcrblished by the HRC as the acceptance criteria. This limit i9 established to insure that damage to the fuel will not occur for these moderate probability events. I note *specificall~r that a sfr:ultaneous loss of four coolant pumps was not*
considered in this tran'sient analysis because it was judged to be of very low probability. Section 14.7.4 of the FSAR states in part: ":!!'or the case of a single stuck rotor there will be some rods for which the transien*t; mrn ratio droJ:ls below 1.30.however the very low probability of this incident allows acceptance of this.condition."* That statement also applies p'.1ilosophicnlly to the very low probability case of a s:i.:r.ml taneous loss of all four primi:..ry coolant pumps.
FSAR Ap:pendix A.2(g) describes the Plant design with respect to flooding as protected up to elevation 590 feet. This provides a margin of 7.3 feet above the highest reported nodern lake level. Six (6) of these 7 .3 feet are described as. an allowance* for seiche, thus, I would conclude that the J?ossibility of a seiche was properly considered in the design of the Plant against f'looding to the 590 foot level. I note that the bottom of the four primary coolant pwnp breakers are mou.~ted at the 590 foot level *
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2.
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A rev.i.ew of question 2 .4 of Amendments 15 and 18 to the FSAR reveals the following key words. They are:
"Maximum increase" "especially severe seiche" *
"shutdown safely" "with or without s:pecial procedures and provisions executed at the time of flooding."
The context of this question is an inextremis situation. It is -intended to convey a very low probability event and asks what the maximum flooding level is that equipment reg_uired to obtain and maintain a safe shutdo~*m condition would be functional. The answer given was 594 feet 8 inches and states that equipment required to obtain and maintain a safe shutdown*condition would not be flooded until water level exceeded thi.s value. This question did not intend to imply that the four primary coolant pu.mps could not trip sequentially *. The probability.is conveyed as extremely low as compared to anticipated transients.
The six foot allowance for a seiche appears conservative. Section 2.2.2(a) shows the greatest level change due to a seiche over an 105 year period to be 6 feet at Michi"g!?.n City, Indiana and 0 at the same time at Holland, J:ld.chigan.
Further, J~IT(eiser's calculations show the maximum level .at Palisades to be much less than 6 ~eet
- Therefore, I have concluded that the FSAR has appropriately considered and evaluated the effects _of seiches on the Palisades Plant and the design and construction of the Palisades Plant was in accordance with the requirements of the FSAR. Thus, my conclusion is that this item is not an unreviewed safety qu:-;!stion and is not reportable in accordance with Section 6. 9.2 a-8 of the Technical Specifications. Further, I believe that this event report should be closed out. With PRC concurrence, I will inform the NRC that we no longer consider this event reportable and are therefore canceling it *