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| | issue date = 02/04/2013 | | | issue date = 02/04/2013 |
| | title = IR 05000255-13-007, 01/07/2013 - 01/24/2013, Palisades Nuclear Plant; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications | | | title = IR 05000255-13-007, 01/07/2013 - 01/24/2013, Palisades Nuclear Plant; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications |
| | author name = Daley R C | | | author name = Daley R |
| | author affiliation = NRC/RGN-III/DRS/EB3 | | | author affiliation = NRC/RGN-III/DRS/EB3 |
| | addressee name = Vitale A | | | addressee name = Vitale A |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532 | | {{#Wiki_filter:ruary 4, 2013 |
| -4352 February 4, 2013 Mr. Anthony Vitale Vice-President, Operations Entergy Nuclear Operations, Inc.
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| Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043
| | ==SUBJECT:== |
| -9530
| | PALISADES NUCLEAR PLANT EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000255/2013007 |
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| SUBJECT: PALISADES NUCLEAR PLANT EVALUATION S OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000 255/2013007
| | ==Dear Mr. Vitale:== |
| | On January 24, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your Palisades Nuclear Plant. The enclosed inspection report documents the inspection results which were discussed on January 24, 2013, with you and other members of your staff. |
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| ==Dear Mr. Vitale:==
| | The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license. |
| On January 24, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your Palisades Nuclear Plant
| |
| . The enclosed inspection report documents the inspection results which were discussed on January 24, 2013
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| , with you and other members of your staff.
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| The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
| | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. |
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| No findings were identified during this inspection | | No findings were identified during this inspection. |
| . In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading
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| -rm/adams.html (the Public Electronic Reading Room).
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| Sincerely,/RA/ Robert C. Daley, Chie f Engineering Branch 3 Division of Reactor Safety Docket Nos.
| | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
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| 50-255 License Nos. DPR-20 | | Sincerely, |
| | /RA/ |
| | Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-255 License Nos. DPR-20 |
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| ===Enclosure:=== | | ===Enclosure:=== |
| Inspection Report 05000255/201 3 00 7 | | Inspection Report 05000255/2013007 w/Attachment: Supplemental Information |
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| ===w/Attachment:=== | | REGION III== |
| Supplemental Information cc: Distribution via ListServ
| | Docket No.: 50-255 License No.: DPR-20 Report No.: 05000255/2013007 Licensee: Entergy Nuclear Operations, Inc. |
| Ž Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket No.:
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| 50-255 License No.: | |
| DPR-20 Report No.: | |
| 05000255/201 3 0 07 Licensee: | |
| Entergy Nuclear Operations, Inc. | |
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| Facility: | | Facility: Palisades Nuclear Plant Location: Covert, MI Dates: January 7, 2013 - January 24, 2013 Inspectors: A. Dahbur, Senior Reactor Inspector, Lead D. Szwarc, Reactor Inspector I. Hafeez, Reactor Inspector Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure |
| Palisades Nuclear Plant Location: | |
| Covert, MI Dates: January 7, 201 3 - January 24, 201 3 Inspectors: | |
| A. Dahbur, Senior Reactor Inspector, Lead D. Szwarc, Reactor Inspector I. Hafeez, Reactor Inspector Approved by: | |
| Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety 1 Enclosure | |
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| =SUMMARY= | | =SUMMARY= |
| IR 05000255/2013007, 01/07/2013 | | IR 05000255/2013007, 01/07/2013 - 01/24/2013; Palisades Nuclear Plant; Evaluations of |
| | |
| - 01/24/2013 | |
| ; Palisades Nuclear Plant | |
| ; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications. | |
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| This report covers a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG
| | Changes, Tests, or Experiments and Permanent Plant Modifications. |
| -1649, "Reactor Oversight Process," Revision 4, dated December 2006.
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| A. No findings of significance were identified.
| | This report covers a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, |
| | Revision 4, dated December 2006. |
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| N RC-Identified and Self-Revealed Findings B. No violations of significance were identified.
| | ===NRC-Identified=== |
| | and Self-Revealed Findings No findings of significance were identified. |
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| ===Licensee-Identified Violations=== | | ===Licensee-Identified Violations=== |
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| 1. REACTOR SAFETY
| | No violations of significance were identified. |
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| =REPORT DETAILS= | | =REPORT DETAILS= |
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| ===Cornerstone:=== | | ==REACTOR SAFETY== |
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| Initiating Events, Mitigating Systems, and Barrier Integrity 1R17 Evaluation s of Changes, Tests, or Experiments and Permanent Plant Modifications
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| ===.1 === | | ===Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity=== |
| | {{a|1R17}} |
| | ==1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications== |
| {{IP sample|IP=IP 71111.17}} | | {{IP sample|IP=IP 71111.17}} |
| a. Evaluation of Changes, Tests, or Experiments From January 7, 2013 through January 24, 2013
| | ===.1 Evaluation of Changes, Tests, or Experiments=== |
| , the inspectors reviewed five safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine whether the evaluations were adequate and that prior NRC
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| -approval was obtained as appropriate. The minimum sample size of six safety evaluations was not achieved, because the licensee had only performed five safety evaluations during the sample period. The inspectors also reviewed fourteen screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:
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| Inspection Scope the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required; the safety issue requiring the change, tests or experiment was resolved; the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and the design and licensing basis documentation was updated to reflect the change.
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| | |
| The inspectors used, in part, Nuclear Energy Institute (NEI) 96
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| -07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, "10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments."
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| This inspection constituted five samples of evaluations and fourteen samples of changes as defined in IP
| | ====a. Inspection Scope==== |
| | From January 7, 2013 through January 24, 2013, the inspectors reviewed five safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine whether the evaluations were adequate and that prior NRC-approval was obtained as appropriate. The minimum sample size of six safety evaluations was not achieved, because the licensee had only performed five safety evaluations during the sample period. The inspectors also reviewed fourteen screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if: |
| | * the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required; |
| | * the safety issue requiring the change, tests or experiment was resolved; |
| | * the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and |
| | * the design and licensing basis documentation was updated to reflect the change. |
|
| |
|
| ==71111.17 - 04.==
| | The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments. |
| b. No findings of significance were identified.
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| Findings 3 Enclosure
| | This inspection constituted five samples of evaluations and fourteen samples of changes as defined in IP 71111.17-04. |
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| ===.2 a. Permanent Plant Modifications=== | | ====b. Findings==== |
| | No findings of significance were identified. |
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| From January 7, 2013 through January 24, 2013
| | ===.2 Permanent Plant Modifications=== |
| , the inspectors reviewed eight permanent plant modification s including two design basis calculations that had been installed in the plant or modified during the last three years. This review included in
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| -plant walkdowns for portions of the modifie d Containment Spray, Station Battery Charger and Emergency Diesel Generator starting air systems.
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| The modifications were selected based upon risk | | ====a. Inspection Scope==== |
| -significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if: | | From January 7, 2013 through January 24, 2013, the inspectors reviewed eight permanent plant modifications including two design basis calculations that had been installed in the plant or modified during the last three years. This review included in-plant walkdowns for portions of the modified Containment Spray, Station Battery Charger and Emergency Diesel Generator starting air systems. The modifications were selected based upon risk-significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if: |
| Inspection Scope the supporting design and licensing basis documentation was updated; the changes were in accordance with the specified design requirements; the procedures and training plans affected by the modification have been adequately updated; the test documentation as required by the applicable test programs has been updated; and post-modification testing adequately verified system operability and/or functionality.
| | * the supporting design and licensing basis documentation was updated; |
| | * the changes were in accordance with the specified design requirements; |
| | * the procedures and training plans affected by the modification have been adequately updated; |
| | * the test documentation as required by the applicable test programs has been updated; and |
| | * post-modification testing adequately verified system operability and/or functionality. |
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| The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an Attachment to this report. | | The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an Attachment to this report. |
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| This inspection constituted eight permanent plant modification samples as defined in IP | | This inspection constituted eight permanent plant modification samples as defined in IP 71111.17-04. |
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| ==71111.17 - 04.==
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| b. No findings were identified.
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| Findings | | ====b. Findings==== |
| | No findings were identified. |
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| ==OTHER ACTIVITIES== | | ==OTHER ACTIVITIES (OA)== |
| (OA) | |
| {{a|4OA2}} | | {{a|4OA2}} |
| ==4OA2 == | | ==4OA2 Problem Identification and Resolution== |
| ===.1 Problem Identification and Resolution===
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| a. Routine Review of Condition Reports From January 7, 2013 through January 24, 2013
| | ===.1 Routine Review of Condition Reports=== |
| , the inspectors reviewed several corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and permanent plant modifications. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to permanent p lant modifications and evaluations of changes, tests, or experiments. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problems into the Inspection Scope
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|
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| 4 Enclosure corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the attachment to this report.
| | ====a. Inspection Scope==== |
| | From January 7, 2013 through January 24, 2013, the inspectors reviewed several corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and permanent plant modifications. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to permanent plant modifications and evaluations of changes, tests, or experiments. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problems into the corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the attachment to this report. |
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| b. No findings of significance were identified. | | ====b. Findings==== |
| | No findings of significance were identified. |
| | {{a|4OA6}} |
| | ==4OA6 Meetings== |
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| Findings
| | ===.1 Exit Meeting Summary=== |
| {{a|4OA6}}
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| ==4OA6 ==
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| ===.1 Meetings O n January 24, 2013, the inspector=== | |
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| s presented the inspection results to Mr. A. Vitale and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.
| | On January 24, 2013, the inspectors presented the inspection results to Mr. A. Vitale and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff. |
|
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| ===Exit Meeting Summary===
| | ATTACHMENT: |
| ATTACHMENT: | |
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| =SUPPLEMENTAL INFORMATION= | | =SUPPLEMENTAL INFORMATION= |
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| Attachment
| | ==KEY POINTS OF CONTACT== |
| SUPPLEMENTAL INFORMATION KEY POINTS OF CONTAC
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| T
| | Licensee |
| : [[contact::A. Vitale]], Site Vice | | : [[contact::A. Vitale]], Site Vice-President |
| -President Licensee | |
| : [[contact::A. Bono]], Design Engineer | | : [[contact::A. Bono]], Design Engineer |
| : [[contact::D. Fitzgibbon]], Design Engineering Manager | | : [[contact::D. Fitzgibbon]], Design Engineering Manager |
| : [[contact::O. Gustafson]], Licensing Manager | | : [[contact::O. Gustafson]], Licensing Manager |
| : [[contact::J. Haumersen]], System Engineering Manager | | : [[contact::J. Haumersen]], System Engineering Manager |
| : [[contact::J. Dills]], Operations Manager | | : [[contact::J. Dills]], Operations Manager |
| : [[contact::C. Plachta]], Quality Assurance Manager | | : [[contact::C. Plachta]], Quality Assurance Manager |
| : [[contact::R. White]], Assistant Operations Manager | | : [[contact::R. White]], Assistant Operations Manager |
| : [[contact::B. Dotson]], Licensing Specialist | | : [[contact::B. Dotson]], Licensing Specialist |
| : [[contact::T. Williams]], General Manager, Plant Operations | | : [[contact::T. Williams]], General Manager, Plant Operations |
| : [[contact::C. Arnone]], Nuclear Safety | | : [[contact::C. Arnone]], Nuclear Safety Assurance Director |
| Assurance Director | |
| : [[contact::C. Sherman]], Radiation Protection Manager | | : [[contact::C. Sherman]], Radiation Protection Manager |
| : [[contact::D. Kennedy]], Senior Engineer | | : [[contact::D. Kennedy]], Senior Engineer |
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Line 144: |
| : [[contact::N. Trela]], System Engineer | | : [[contact::N. Trela]], System Engineer |
| : [[contact::P. Russel]], Production Manager | | : [[contact::P. Russel]], Production Manager |
| | Nuclear Regulatory Commission |
| : [[contact::T. Taylor]], Senior Resident Inspector, Palisades | | : [[contact::T. Taylor]], Senior Resident Inspector, Palisades |
| Nuclear Regulatory Commission
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| LIST OF ITEMS OPENED, CLOSED AND DISCUSS
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| ED NoneOpened, Closed, and Discussed
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| Attachment
| | ==LIST OF ITEMS== |
| LIST OF DOCUMENTS REVIEWED The following is a list of documents reviewed during the inspection. Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort. Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report. | | |
| CALCULATIONS
| | ===OPENED, CLOSED AND DISCUSSED=== |
| Number Description or Title
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| EA-ELEC-AMP-042 Date or Revision
| | ===Opened, Closed, and Discussed=== |
| Pressurizer
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| Heater Current Requirement
| | None Attachment |
| SUT1-2/SUT1-2/ALTC Startup Transformer1
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| -2 Load Tap Changer Automatic Controls
| | ==LIST OF DOCUMENTS REVIEWED== |
| EA-FC-958-04 Calculation to Size and Provide Instrumentation Levels for the Replacement of
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| the Diesel Fuel Oil Tank T
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| -10 with T-10A 3 CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
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| Number Description or Title
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| CR-PAL-97-0355 Date or Revision
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| Procedural Guidance for Opening CV
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| -3070/3071 HPSI Sub Cooling Valves
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| March 11, 1997
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| CR-PLP-2007-04259 Issues Related to EDG Fuel Oil Tank Volume Calculations
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| September 21, 2007
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| CR-PLP-2008-01392 MOC Switch Bayonet Operator With Broken Welds. March 26, 2008
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| CR-PLP-2008-01496 Diesel Fuel Oil Storage Tank T
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| -10A Level Indication Dimension Discrepancy
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| April 1, 2008
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| CR-PLP-2009-03982 50.59 Evaluation for EC8350
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| did not Properly Address Question 2
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| August 19, 2009
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| CR-PLP-2009-04881 Formatting of a Particular Operations Procedure is Prone to Human
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| October 21, 2009
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| CR-PLP-2009-05236 EA-EC8350-04 Acceptance Criteria not Met
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| November 12, 2
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| 009 CR-PLP-2010-05462 2400 Volts Bus 1
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| -C was Reading Low Out of Spec October 22, 2010
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| CR-PLP-2012-1775 PI-1490, K6B Starting Air Pressure Indicator for the Emergency Diesel Generator 1
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| -2, was Reading Abnormally High
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| March 19, 2012
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| DRAWINGS Number Description or Title
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| E-1, Sheet A
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| Date or Revision
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| Single Line Meter and Relay
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| Diagram 11 E-121, Sheet
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| A Schematic Diagram Turbine Control
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| E-136, Sheet 1
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| Schematic Diagram 2400V and 4160V Bus Transfer 31 E-136, Sheet 2
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| Schematic Diagram 2400V and 4160V Bus Transfer 31
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| Attachment | |
| DRAWINGS Number Description or Title
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| E-17, Sheet 9
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| Date or Revision
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| Logic Diagram Generator Trips and fast Transfer 23 M-214, Sheet 1
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| Piping and Instrumentation Diagram, Lube Oil, Fuel Oil
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| and Diesel Generator Systems
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| M-398, Sheet 34
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| Level Settings Diagram, Diesel Oil Storage Tank No. T-10A 9 10 CFR 50.59 EVALUATIONS
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| Number Description or Title
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| 09-0601 Date or Revision
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| Core operating Limits Report (COLR)
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| January 19, 2010
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| 09-0602 EC 8350 - Replace Containment Spray Isolation Valves per GSI
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| -191 Resolution
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| November 16, 2009
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| 09-0680 Radiological Calculations for AST Implementation
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| December, 14, 2009
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| 10-0137 Containment Response for LOCA using Gothic 7.2a
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| July 15, 2010
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| 2-0402 EC 27518 - Motor Control Center Buckets Replacement
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| December 18, 2012
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| CFR 50.59 SCREENINGS
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| Number Description or Title
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| 09-0687 Date or Revision
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| Modify EX-10 0 10-0053 Technical Specifications Basis B
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| -3.8.1 February 11, 2010
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| 10-0065 ESSO-1, Containment Spray Header Fill
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| February 17, 2010
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| 10-0077 SOP-3/Safety Injection and Shutdown Cooling System
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| March 1, 2010
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| 10-0104 Station Power
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| March 11, 2010
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| 10-0180 Balance of Plant Actions Following A Reactor Trip
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| April 26, 2010
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| 10-0361 EC17255, Installation of Vortex
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| Suppression Devices in the Safety Injection Refueling Water Tank, T-58 September 1, 2010
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| 10-0488 Update Load Profile for Battery Test
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| 10-0520 Revise FSAR Description of the Loss of Load Reactor Trip
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| 10-0528 Fast Transfer Test
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| 11-0129 Update EEQ Files for MOV Long Life Grease April 6, 2011
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| 11-0221 SOP-16, Component Cooling Water System October 22, 2010
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| 11-0326 License Basis Document Change
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| Request 10
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| -013 August 18, 2011
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|
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|
| Attachment
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| CFR 50.59 SCREENINGS
| |
| Number Description or Title
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| 11-203 Date or Revision
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| Replace Control Room Subcooling Recorder April 27, 2011
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| 2-0081 EC 34615 - Establish Pickup Setting for Relays 305L and 305
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| -R March 1, 2012
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| MODIFICATIONS
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| Number Description or Title
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| EC 08005 Date or Revision
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| Replacement of 2400 SWGR Cubicle
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| EC 13204 Second Level Voltage Relay
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| EC 16993 Correct Level Settings for Diesel Fuel Oil Storage Tank T
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| -10a April 14, 2010
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| EC 5885 Emergency Diesel Generator 1
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| -1 and 1-2 Starting Air System Reliability Upgrades
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| EC 6432 Palisades Emergency Diesel Generator Diesel Fuel Oil Storage Requirements
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| EC 25561 Startup Transformer 1
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| - 2 Setpoint Change
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| October 25, 2010
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| PROCEDURES
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| Number Description or Title
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| ESSO-14 Date or Revision
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| Flush HPSI Sub
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| -cooling Valves
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| SOP-3 Safety Injection and Shutdown Cooling System 89 SOP-16 Component Cooling Water System
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| ESSO-1 Containment Spray Header Fill
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| Attachment
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| LIST OF ACRONYMS USE
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| D ADAMS Agencywide Documents Access and Management System
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| AR Action Report
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| ASME American Society of Mechanical Engineers
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| CFR Code of Federal Regulations
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| CNO Chief Nuclear Officer
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| DRS Division of Reactor Safety
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| EC Engineering Change
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| FIN Finding HPSI High Pressure Safety Injection
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| IMC Inspection Manual Chapter
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| MOV Motor-Operated Valve
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| NEI Nuclear Energy Institute
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| NRC U.S. Nuclear Regulatory Commission
| |
| PARS Public Available Records System
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| SPAR Standardized Plant Analysis Risk
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| SSC Structures, Systems and Components
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| TS Technical Specification
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| UFSAR Updated Final Safety Analysis Report
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| Mr. Anthony Vitale
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| Vice-President, Operations
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| Entergy Nuclear Operations, Inc.
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| Palisades Nuclear Plant
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| 27780 Blue Star Memorial Highway
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| Covert, MI 49043
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| -9530 SUBJECT: PALISADES NUCLEAR PLANT EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000255/2013007
| |
| Dear Mr. Vitale:
| |
| On January 24, 2013, the
| |
| : [[contact::U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes]], Tests, or Experiments and Permanent Plant Modifications inspection at your Palisades Nuclear Plant. The enclosed inspection report documents the inspection results which were discussed on
| |
| January 24, 2013, with you and other members of your
| |
| staff. The inspection examined activities conducted under your license as they relate to safety and compliance
| |
| with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
| |
| No findings were identified during this inspection.
| |
| In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading
| |
| -rm/adams.html
| |
| (the Public Electronic Reading Room).
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| Sincerely,
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| /RA/ Robert
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| : [[contact::C. Daley]], Chief
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| Engineering Branch 3
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| Division of Reactor Safety
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| Docket Nos. 50
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| -255 License Nos. DPR
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| -20 Enclosure:
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| Inspection Report 05000255/201
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| 00 7 w/Attachment: Supplemental Information
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| cc: Distribution via ListServŽ
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| DISTRIBUTIONSee next page
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| : DOCUMENT NAME:
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| G:\DRSIII\DRS\Work in Progress
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| \-PAL 2013 007
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| MOD 50 59 AKD.docx
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| Publicly Available
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| Non-Publicly Available
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| Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy
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| OFFICE RIII RIII RIII RIII NAME ADahbur:ls
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| RCDaley DATE 02/04/13 02/04/13 OFFICIAL RECORD COPY
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| Letter to Mr. Mr. Anthony Vitale
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| from Mr. Robert C. Daley
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| dated February 4, 2013. SUBJECT: PALISADES NUCLEAR PLANT EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT
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| 05000 255/2013007 DISTRIBUTIONJohn Cassidy
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| : RidsNrrPMPalisades Resource
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| RidsNrrDorlLpl3
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| -1 Resource
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| RidsNrrDirsIrib Resource
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| Chuck Casto
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| Cynthia Pederson
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| Steven Orth
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| Allan Barker
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| Christine Lipa
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| Carole Ariano
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| Linda Linn
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| DRPIII DRSIII Tammy Tomczak
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| ROPreports.Resource@nrc.gov
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| }} | | }} |
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Category:Inspection Report
MONTHYEARIR 05000255/20244022024-09-0606 September 2024
Public: Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2024402
IR 05000255/20240022024-08-0909 August 2024
NRC Inspection Report No. 05000255/2024002
IR 05000255/20240112024-07-15015 July 2024
Nuclear Plant - Restart Inspection Report 05000255/2024011
IR 05000255/20240012024-05-10010 May 2024
NRC Inspection Report No. 05000255/2024001
IR 05000255/20244012024-04-0909 April 2024
– Decommissioning Security Inspection Report 05000255/2024401
IR 05000255/20240102024-03-20020 March 2024
Plant Reference Simulator Inspection Report 05000255/2024010
IR 05000255/20230042024-02-20020 February 2024
NRC Inspection Report 05000255/2023004(DRSS) Holtec Decommissioning International, LLC, Palisades Nuclear Plant
IR 05000255/20230032023-10-0404 October 2023
NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant
IR 05000255/20230022023-07-19019 July 2023
NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant
IR 05000255/20220032022-12-28028 December 2022
NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant
IR 05000255/20224012022-11-0909 November 2022
Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401
IR 05000255/20220022022-08-0303 August 2022
Integrated Inspection Report 05000255/2022002
IR 05000255/20220012022-05-13013 May 2022
Integrated Inspection Report 05000255/2022001
IR 05000255/20220102022-04-0101 April 2022
Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000255/2022010
IR 05000255/20210062022-03-0202 March 2022
Annual Assessment Letter for Palisades Nuclear Plant, Unit 1, (Report 05000255/2021006)
IR 05000255/20210102022-02-24024 February 2022
Triennial Fire Protection Inspection Report 05000255/2021010
IR 05000255/20210042022-02-0808 February 2022
Integrated Inspection Report 05000255/2021004 and Exercise of Enforcement Discretion
IR 05000255/20214042021-11-15015 November 2021
NRC Independent Spent Fuel Storage Installation Security Inspection Report 05000255/2021404 and 07200007/2021401
IR 05000255/20210032021-11-0303 November 2021
Integrated Inspection Report 05000255/2021003
IR 05000255/20214032021-10-21021 October 2021
Material Control and Accounting Program Inspection Report 05000255/2021403
IR 05000255/20214022021-10-0606 October 2021
Security Baseline Inspection Report 05000255/2021402
IR 05000255/20210052021-09-0101 September 2021
Updated Inspection Plan for Palisades Nuclear Plant (Report 05000255/2021005)
IR 05000255/20210022021-08-10010 August 2021
Integrated Inspection Report 05000255/2021002
ML21197A0322021-07-21021 July 2021
Review of the Fall 2020 Steam Generator Tube Inspection Report
IR 05000255/20210012021-05-12012 May 2021
Integrated Inspection Report 05000255/2021001
IR 05000255/20214012021-04-14014 April 2021
Security Baseline Inspection Report 05000255/2021401
IR 05000255/20200062021-03-0404 March 2021
Annual Assessment Letter for Palisades Nuclear Plant (Report 05000255/2020006)
IR 05000255/20200042021-02-11011 February 2021
Integrated Inspection Report 05000255/2020004
IR 05000255/20204012021-01-0606 January 2021
Security Baseline Inspection Report 05000255/2020401
ML20342A1812020-12-10010 December 2020
Security Inspection Report Cover Letter 05000255/2020420
IR 05000255/20204202020-12-10010 December 2020
Security Inspection Report 05000255/2020420
IR 05000255/20204022020-11-30030 November 2020
Cyber Security Inspection Report 05000255/2020402
IR 05000255/20205012020-11-20020 November 2020
Emergency Preparedness Inspection Report 05000255/2020501
IR 05000255/20200032020-11-13013 November 2020
Integrated Inspection Report 05000255/2020003
IR 05000255/20200052020-09-0101 September 2020
Updated Inspection Plan for Palisades Nuclear Plant (Report 05000255/2020005)
IR 05000255/20200102020-08-24024 August 2020
Biennial Problem Identification and Resolution Inspection Report 05000255/2020010
IR 05000255/20203012020-08-13013 August 2020
NRC Initial License Examination Report 05000255/2020301
IR 05000255/20200022020-08-11011 August 2020
Integrated Inspection Report 05000255/2020002 and Exercise of Enforcement Discretion
IR 05000255/20010082020-05-12012 May 2020
Final ASP Analysis - Palisades (IR 050002552001008)
IR 05000255/20200012020-05-12012 May 2020
Integrated Inspection Report 05000255/2020001
IR 05000255/20200112020-04-21021 April 2020
Design Basis Assurance Inspection (Teams) Inspection Report 05000255/2020011
IR 05000254/20204012020-03-23023 March 2020
Security Baseline Inspection Report 05000254/2020401 and 05000265/2020401
IR 05000255/20190062020-03-0303 March 2020
Annual Assessment Letter Palisades Nuclear Plant (Report 05000255/2019006)
IR 05000255/20190042020-01-28028 January 2020
Integrated Inspection Report 05000255/2019004 and 07200007/2019001
ML19357A2752019-12-23023 December 2019
Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000255/2020011
IR 05000255/20190112019-11-27027 November 2019
Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000255/2019011
IR 05000255/20194112019-11-25025 November 2019
Security Baseline Inspection Report 05000255/2019411 and Independent Spent Fuel Storage Security Inspection Report 07200007/2019401 (Cover Letter Only) (DRS-M.Ziolkowski)
IR 05000255/20190032019-11-14014 November 2019
Integrated Inspection Report 05000255/2019003
IR 05000255/20190102019-10-29029 October 2019
Reissue - Palisades Nuclear Plant - Design Basis Assurance Inspection (Programs) Inspection Report 05000255/2019010
ML19294A2872019-10-21021 October 2019
Design Basis Assurance Inspection (Programs) Inspection Report 05000255/2019010
2024-09-06
[Table view]
Category:Letter
MONTHYEARPNP 2024-014, Request for USNRC to Rescind Approved Exemption Requests for 140.11(a)(4) and 50.54(w)(1), Reduction of Insurances2024-10-0909 October 2024
Request for USNRC to Rescind Approved Exemption Requests for 140.11(a)(4) and 50.54(w)(1), Reduction of Insurances
PNP 2024-037, Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-0202024-10-0404 October 2024
Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-020
ML24267A2962024-10-0101 October 2024
Summary of Conference Call Regarding Steam Generator Tube Inspections
ML24263A1712024-09-20020 September 2024
Environmental Request for Additional Information
ML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
ML24219A4202024-09-12012 September 2024
Change in Estimated Hours and Review Schedule for Licensing Actions Submitted to Support Resumption of Power Operations (Epids L-2023-LLE-0025, L-2023-LLM-0005, L-2023-LLA-0174, L-2024-LLA-0013, L-2024-LLA-0060, L-2024-LLA-0071)
IR 05000255/20244022024-09-0606 September 2024
Public: Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2024402
PNP 2024-029, Notice of Payroll Transition at Palisades Nuclear Plant2024-08-15015 August 2024
Notice of Payroll Transition at Palisades Nuclear Plant
IR 05000255/20240022024-08-0909 August 2024
NRC Inspection Report No. 05000255/2024002
PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024
Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0
PNP 2024-032, Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations2024-07-31031 July 2024
Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations
ML24206A0572024-07-25025 July 2024
PRM-50-125 - Letter to Alan Blind; Docketing of Petition for Rulemaking and Sufficiency Review Status (10 CFR Part 50)
PNP 2024-033, Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations2024-07-24024 July 2024
Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations
PNP 2024-031, Response to RIS 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-07-18018 July 2024
Response to RIS 2024-01, Preparation and Scheduling of Operator Licensing Examinations
IR 05000255/20240112024-07-15015 July 2024
Nuclear Plant - Restart Inspection Report 05000255/2024011
PNP 2024-027, Supplement to License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2024-07-0909 July 2024
Supplement to License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations
ML24183A1382024-07-0202 July 2024
Tribal Letter - Lac Du Flambeau Band of Lake Superior Chippewa Indians
ML24137A0142024-07-0202 July 2024
OEDO-24-00011 - 2.206 Petition for Misuse of Palisades Decommissioning Trust Fund (EPID L-2023-CRS-0008) - Letter
ML24183A1492024-07-0101 July 2024
Tribal Letter - Pokagon Band of Potawatomi Indians
ML24156A0222024-07-0101 July 2024
Initiation of Scoping Process to Prepare an Environmental Assessment for the Environmental Review of Holtec Decommissioning International, Llc’S Licensing and Regulatory Requests for Reauthorization of Power Operations at Palisades EPID L-2
ML24183A1552024-07-0101 July 2024
Tribal Letter - Red Lake Band of Chippewa Indians
ML24183A1542024-07-0101 July 2024
Tribal Letter Red Cliff Band of Lake Superior Chippewa Indians
ML24172A0032024-07-0101 July 2024
Letter to L. Powers, Mackinac Bands of Chippewa and Ottawa Indians Re Initiation of Scoping Process for Environ Review Holtec Decommissioning Intl, LLC Request for Reauthorization of Power Ops-Palisades
ML24183A1332024-07-0101 July 2024
Tribal Letter-Forest County Potawatomi Community
ML24183A1582024-07-0101 July 2024
Tribal Letter Sault Ste. Marie Tribe of Chippewa Indians
ML24183A1302024-07-0101 July 2024
Tribal Letter-Chippewa Cree Indians of the Rocky Boys Reservation
ML24183A1282024-07-0101 July 2024
Tribal letter-Bay Mills Indian Community
ML24183A1532024-07-0101 July 2024
Tribal Letter Quechan Tribe of the Fort Yuma Indian Reservation
ML24183A1572024-07-0101 July 2024
Tribal Letter - Saint Croix Chippewa Indians of Wisconsin
ML24183A1462024-07-0101 July 2024
Tribal letter-Mille Lacs Band of Ojibwe
ML24183A1422024-07-0101 July 2024
Tribal Letter-Little Traverse Bay Bands of Odawa Indians
ML24183A1312024-07-0101 July 2024
Tribal Letter-Citizen Potawatomi Nation
ML24163A0552024-07-0101 July 2024
Rebecca Held Knoche NOAA-Palisades-NOI to Conduct Scoping Process and Prepare an EA - EPID No. L-2024-LNE-0003-Docket No. 50-0255
ML24163A2392024-07-0101 July 2024
Sara Thompson, Michigan DNR-Palisades-NOI to Conduct Scoping Process and Prepare an EPID No. L-2024-LNE-0003-Docket No. 50-0255
ML24155A0102024-07-0101 July 2024
Quentin L. Messer Jr., Michigan Econ-Palisades-NOI to Conduct Scoping Process and Prep an EA-EPID No. L-2024-LNE-0003 Docket No.50-0255P
ML24155A0032024-07-0101 July 2024
Kathy Kowal, Us EPA Region 5-Palisades-NOI to Cibdyct Scoping Process and Prepare an EA EPID L-2024-LNE-0003
ML24163A0832024-07-0101 July 2024
Ltr to R Schumaker SHPO Re Initiation of Scoping Process, Section 106 Consult for Env Rev of HDI, LLC Request for Reauth of Power Operations at Palisades Nuclear Plant
ML24183A1342024-07-0101 July 2024
Tribal Letter-Grand Portage Band of Lake Superior Chippewa
ML24183A1392024-07-0101 July 2024
Tribal Letter-Lac Vieux Desert Band of Lake Superior Chippewa Indians
ML24183A1272024-07-0101 July 2024
Tribal Letter-Bad River Band of the Lake Superior Tribe of Chippewa
ML24183A1412024-07-0101 July 2024
Tribal Letter-Little River Band of Ottawa Indians
ML24163A1922024-07-0101 July 2024
Jeremy Rubio, Dept of Env, Great Lakes and Energy, Kalamazoo District-Palisades-NOI to Conduct Scoping Process and Prepare an EA EPID No. L-2024-LNE-0003 Docket No.50-0255
ML24183A1322024-07-0101 July 2024
Tribal Letter-Fond Du Lac Band of Lake Superior Chippewa
ML24183A1592024-07-0101 July 2024
Tribal letter-Sokaogon Chippewa Community
ML24163A0822024-07-0101 July 2024
Ltr to J Loichinger Achp Re Initiation of Scoping Process, Section 106 Consult for Env Rev of HDI, LLC Request for Reauth of Power Operations at Palisades Nuclear Plant
ML24183A1252024-07-0101 July 2024
Letter to G. Gould, Swan Creek Black River Confederated Ojibwa-Init of Scoping Process for the Env Rev of Holtec Decommissioning Intl, LLC Request for Reauth of Power Ops at Palisades
ML24183A1352024-07-0101 July 2024
Tribal Letter-Hannahville Indian Community
ML24183A1442024-07-0101 July 2024
Tribal Letter - Menominee Indian Tribe of Wisconsin
ML24183A1502024-07-0101 July 2024
Tribal Letter - Prarie Band Potawatomi Nation
ML24183A1452024-07-0101 July 2024
Tribal Letter - Miami Tribe of Oklahoma
2024-09-06
[Table view] |
Text
ruary 4, 2013
SUBJECT:
PALISADES NUCLEAR PLANT EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000255/2013007
Dear Mr. Vitale:
On January 24, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your Palisades Nuclear Plant. The enclosed inspection report documents the inspection results which were discussed on January 24, 2013, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
No findings were identified during this inspection.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-255 License Nos. DPR-20
Enclosure:
Inspection Report 05000255/2013007 w/Attachment: Supplemental Information
REGION III==
Docket No.: 50-255 License No.: DPR-20 Report No.: 05000255/2013007 Licensee: Entergy Nuclear Operations, Inc.
Facility: Palisades Nuclear Plant Location: Covert, MI Dates: January 7, 2013 - January 24, 2013 Inspectors: A. Dahbur, Senior Reactor Inspector, Lead D. Szwarc, Reactor Inspector I. Hafeez, Reactor Inspector Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure
SUMMARY
IR 05000255/2013007, 01/07/2013 - 01/24/2013; Palisades Nuclear Plant; Evaluations of
Changes, Tests, or Experiments and Permanent Plant Modifications.
This report covers a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process,
Revision 4, dated December 2006.
NRC-Identified
and Self-Revealed Findings No findings of significance were identified.
Licensee-Identified Violations
No violations of significance were identified.
REPORT DETAILS
REACTOR SAFETY
1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
Main article: IP 71111.17
.1 Evaluation of Changes, Tests, or Experiments
a. Inspection Scope
From January 7, 2013 through January 24, 2013, the inspectors reviewed five safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine whether the evaluations were adequate and that prior NRC-approval was obtained as appropriate. The minimum sample size of six safety evaluations was not achieved, because the licensee had only performed five safety evaluations during the sample period. The inspectors also reviewed fourteen screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:
- the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;
- the safety issue requiring the change, tests or experiment was resolved;
- the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
- the design and licensing basis documentation was updated to reflect the change.
The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments.
This inspection constituted five samples of evaluations and fourteen samples of changes as defined in IP 71111.17-04.
b. Findings
No findings of significance were identified.
.2 Permanent Plant Modifications
a. Inspection Scope
From January 7, 2013 through January 24, 2013, the inspectors reviewed eight permanent plant modifications including two design basis calculations that had been installed in the plant or modified during the last three years. This review included in-plant walkdowns for portions of the modified Containment Spray, Station Battery Charger and Emergency Diesel Generator starting air systems. The modifications were selected based upon risk-significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if:
- the supporting design and licensing basis documentation was updated;
- the changes were in accordance with the specified design requirements;
- the procedures and training plans affected by the modification have been adequately updated;
- the test documentation as required by the applicable test programs has been updated; and
- post-modification testing adequately verified system operability and/or functionality.
The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an Attachment to this report.
This inspection constituted eight permanent plant modification samples as defined in IP 71111.17-04.
b. Findings
No findings were identified.
OTHER ACTIVITIES (OA)
4OA2 Problem Identification and Resolution
.1 Routine Review of Condition Reports
a. Inspection Scope
From January 7, 2013 through January 24, 2013, the inspectors reviewed several corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and permanent plant modifications. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to permanent plant modifications and evaluations of changes, tests, or experiments. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problems into the corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the attachment to this report.
b. Findings
No findings of significance were identified.
4OA6 Meetings
.1 Exit Meeting Summary
On January 24, 2013, the inspectors presented the inspection results to Mr. A. Vitale and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- A. Vitale, Site Vice-President
- A. Bono, Design Engineer
- D. Fitzgibbon, Design Engineering Manager
- O. Gustafson, Licensing Manager
- J. Haumersen, System Engineering Manager
- J. Dills, Operations Manager
- C. Plachta, Quality Assurance Manager
- R. White, Assistant Operations Manager
- B. Dotson, Licensing Specialist
- T. Williams, General Manager, Plant Operations
- C. Arnone, Nuclear Safety Assurance Director
- C. Sherman, Radiation Protection Manager
- D. Kennedy, Senior Engineer
- G. Heisterman, Maintenance Manager
- M. Mlynarek, Chemistry Manager
- N. Trela, System Engineer
- P. Russel, Production Manager
Nuclear Regulatory Commission
- T. Taylor, Senior Resident Inspector, Palisades
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened, Closed, and Discussed
None Attachment
LIST OF DOCUMENTS REVIEWED
