IR 05000255/2013007
| ML13036A150 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/04/2013 |
| From: | Daley R C Engineering Branch 3 |
| To: | Vitale A Entergy Nuclear Operations |
| Alan Dahbur | |
| References | |
| IR-13-007 | |
| Download: ML13036A150 (13) | |
Text
February 4, 2013
Mr. Anthony Vitale Vice-President, Operations Entergy Nuclear Operations, Inc. Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530
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 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).
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 cc: Distribution via ListServŽ Enclosure U. S. NUCLEAR REGULATORY COMMISSION 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 1 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 NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006. A. No findings of significance were identified.
NRC-Identified
and Self-Revealed Findings B. No violations of significance were identified.
Licensee-Identified Violations
1. REACTOR SAFETY
REPORT DETAILS
Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity 1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
.1
a. Evaluation of Changes, Tests, or 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: 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. 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. No findings of significance were identified. Findings 3 Enclosure
.2 a. Permanent Plant Modifications 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 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. No findings were identified. Findings
OTHER ACTIVITIES (OA)
4OA2
.1 Problem Identification and Resolution
a. Routine Review of Condition Reports 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 Inspection Scope 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.
b. No findings of significance were identified. Findings
4OA6
.1 Meetings 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. Exit Meeting Summary ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
- A. Vitale, Site Vice-President Licensee
- 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
- T. Taylor, Senior Resident Inspector, Palisades Nuclear Regulatory Commission
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
NoneOpened, Closed, and
Discussed
Attachment
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 Number Description or Title
- EA-ELEC-AMP-042 Date or Revision Pressurizer Heater Current Requirement 0
- SUT1-2/SUT1-2/ALTC Startup Transformer1-2 Load Tap Changer Automatic Controls 1
- EA-FC-958-04 Calculation to Size and Provide Instrumentation Levels for the Replacement of the Diesel Fuel Oil Tank T-10 with T-10A 3
- CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED Number Description or Title
- CR-PAL-97-0355 Date or Revision Procedural Guidance for Opening
- CV-3070/3071 HPSI Sub Cooling Valves March 11, 1997
- CR-PLP-2007-04259 Issues Related to EDG Fuel Oil Tank Volume Calculations September 21, 2007
- CR-PLP-2008-01392 MOC Switch Bayonet Operator With Broken Welds. March 26, 2008
- CR-PLP-2008-01496 Diesel Fuel Oil Storage Tank T-10A Level Indication Dimension Discrepancy April 1, 2008
- CR-PLP-2009-03982 50.59 Evaluation for EC8350 did not Properly Address Question 2 August 19, 2009
- CR-PLP-2009-04881 Formatting of a Particular Operations Procedure is Prone to Human October 21, 2009
- EA-EC8350-04 Acceptance Criteria not Met November 12, 2009
- CR-PLP-2010-05462 2400 Volts Bus 1-C was Reading Low Out of Spec October 22, 2010
- PI-1490, K6B Starting Air Pressure Indicator for the Emergency Diesel Generator 1-2, was Reading Abnormally High March 19, 2012
- DRAWINGS Number Description or Title E-1, Sheet A Date or Revision Single Line Meter and Relay Diagram 11 E-121, Sheet 1A Schematic Diagram Turbine Control 8 E-136, Sheet 1 Schematic Diagram 2400V and 4160V Bus Transfer 31 E-136, Sheet 2 Schematic Diagram 2400V and 4160V Bus Transfer 31
- Attachment DRAWINGS Number Description or Title E-17, Sheet 9 Date or Revision Logic Diagram Generator Trips and fast Transfer 23 M-214, Sheet 1 Piping and Instrumentation Diagram, Lube Oil, Fuel Oil and Diesel Generator Systems 77 M-398, Sheet 34 Level Settings Diagram, Diesel Oil Storage Tank No. T-10A 9
- 10
- CFR 50.59 EVALUATIONS Number Description or Title 09-0601 Date or Revision Core operating Limits Report (COLR) January 19, 2010 09-0602
- EC 8350 - Replace Containment Spray Isolation Valves per
- GSI-191 Resolution November 16, 2009 09-0680 Radiological Calculations for AST Implementation December, 14, 2009 10-0137 Containment Response for LOCA using Gothic 7.2a July 15, 2010 12-0402
- EC 27518 - Motor Control Center Buckets Replacement December 18, 2012
- 10
- CFR 50.59 SCREENINGS Number Description or Title 09-0687 Date or Revision Modify
- EX-10 0 10-0053 Technical Specifications Basis B-3.8.1 February 11, 2010 10-0065
- ESSO-1, Containment Spray Header Fill February 17, 2010 10-0077
- SOP-3/Safety Injection and Shutdown Cooling System March 1, 2010 10-0104 Station Power March 11, 2010 10-0180 Balance of Plant Actions Following A Reactor Trip April 26, 2010 10-0361 EC17255, Installation of Vortex Suppression Devices in the Safety Injection Refueling Water Tank, T-58 September 1, 2010 10-0488 Update Load Profile for Battery Test 0 10-0520 Revise FSAR Description of the Loss of Load Reactor Trip 0 10-0528 Fast Transfer Test 0 11-0129 Update EEQ Files for MOV Long Life Grease April 6, 2011 11-0221
- SOP-16, Component Cooling Water System October 22, 2010 11-0326 License Basis Document Change Request 10-013 August 18, 2011
- Attachment 10
- CFR 50.59 SCREENINGS Number Description or Title 11-203 Date or Revision Replace Control Room Subcooling Recorder April 27, 2011 12-0081
- EC 34615 - Establish Pickup Setting for Relays 305L and 305-R March 1, 2012
- MODIFICATIONS Number Description or Title
- EC 13204 Second
- Level Voltage Relay 0
- EC 16993 Correct Level Settings for Diesel Fuel Oil Storage Tank T-10a April 14, 2010
- EC 5885 Emergency Diesel Generator 1-1 and 1-2 Starting Air System Reliability Upgrades 0
- EC 6432 Palisades Emergency Diesel Generator Diesel Fuel Oil Storage Requirements 1
- EC 25561 Startup Transformer 1 - 2 Setpoint Change October 25, 2010
- PROCEDURES Number Description or Title
- ESSO-14 Date or Revision Flush HPSI Sub-cooling Valves 0
- SOP-3 Safety Injection and Shutdown Cooling System 89
- SOP-16 Component Cooling Water System 38
- ESSO-1 Containment Spray Header Fill 14
- Attachment
LIST OF ACRONYMS
- USED [[]]
- NRC [[]]
UFSAR Updated Final Safety Analysis Report
Mr. Anthony Vitale Vice-President, Operations Entergy Nuclear Operations, Inc. Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert,
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- 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 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
- NRC 's "Rules of Practice," a copy of this letter, its enclosure, will be available electronically for public inspection in the
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
- DPR -20 Enclosure: Inspection Report 05000255/2013007 w/Attachment: Supplemental Information cc: Distribution via ListServŽ DISTRIBUTIONSee next page : DOCUMENT NAME: G:\DRSIII\DRS\Work in Progress\-PAL 2013
- AKD. docx Publicly Available Non-Publicly Available 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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