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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 SUBJECT: PALISADES NUCLEAR PLANT EVALUATION S OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000 255/2013007
| | PALISADES NUCLEAR PLANT EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000255/2013007 |
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| ==Dear Mr. Vitale:== | | ==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 | | 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 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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| 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 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. |
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| No findings were identified during this inspection | | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. |
| . 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). | | No findings were identified during this inspection. |
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| | 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, | | Sincerely, |
| /RA/ Robert C. Daley, Chie f Engineering Branch 3 Division of Reactor Safety Docket Nos. | | /RA/ |
| | Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-255 License Nos. DPR-20 |
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| 50-255 License Nos. DPR-20 Enclosure:
| | ===Enclosure:=== |
| Inspection Report 05000255/201 3 00 7 w/Attachment: Supplemental Information cc: Distribution via ListServ | | Inspection Report 05000255/2013007 w/Attachment: Supplemental Information |
| Ž Enclosure U. S. NUCLEAR REGULATORY COMMISSION
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| ==REGION III==
| | REGION III== |
| Docket No.: | | Docket No.: 50-255 License No.: DPR-20 Report No.: 05000255/2013007 Licensee: Entergy Nuclear Operations, Inc. |
| 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 |
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| - 01/24/2013
| | Changes, Tests, or Experiments and Permanent Plant Modifications. |
| ; Palisades Nuclear Plant
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| ; 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 | | 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, |
| -1649, "Reactor Oversight Process," Revision 4, dated December 2006. | | Revision 4, dated December 2006. |
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| A. No findings of significance were identified.
| | ===NRC-Identified=== |
| | | and Self-Revealed Findings No findings of significance were identified. |
| N RC-Identified and Self-Revealed Findings B. No violations 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 | | ===Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity=== |
| | | {{a|1R17}} |
| ===.1 ===
| | ==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
| | ====a. Inspection Scope==== |
| -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."
| | 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. |
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| This inspection constituted five samples of evaluations and fourteen samples of changes as defined in IP 71111.17-04. b. No findings of significance were identified.
| | 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. |
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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 71111.17-04. b. No findings were identified. | | This inspection constituted eight permanent plant modification samples as defined in IP 71111.17-04. |
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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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| 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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| : [[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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| Attachment
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| CFR 50.59 SCREENINGS
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| 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
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| 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
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| Dear Mr. Vitale:
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| On January 24, 2013, the
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| : [[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
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| January 24, 2013, with you and other members of your
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| 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.
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| 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
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| (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 05000255/20230032023-10-0404 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
IR 05000255/20190052019-08-28028 August 2019
Updated Inspection Plan for Palisades Nuclear Plant, Unit 1 (Report 05000255/2019005)
ML19210D4022019-07-29029 July 2019
Ltr. 07/29/19 Palisades Nuclear Plant - Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection; Inspection Report 05000255/2019011 (DRS-D.Szwarc)
IR 05000255/20190022019-07-26026 July 2019
Integrated Inspection Report 05000255/2019002
IR 05000255/20194102019-06-0404 June 2019
NRC Security Baseline Inspection Report 05000255/2019410 (Cover Letter Only) (DRS-N.Egan)
IR 05000255/20190012019-05-10010 May 2019
Errata - Palisades Nuclear Plant, Unit 1 - NRC Integrated Inspection Report 05000255/2019001
ML19123A1742019-05-0303 May 2019
NRC Integrated Inspection Report 05000255/2019001
IR 05000255/20150032019-04-11011 April 2019
Errata - Palisades Nuclear Plant, NRC Integrated Inspection Report 05000255/2015003 (DRS-K.Stoedter)
2023-07-19
[Table view]
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] |
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
