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=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532
[[Issue date::February 4, 2013]]
-4352 February 4, 2013 Mr. Anthony Vitale Vice-President, Operations Entergy Nuclear Operations, Inc.


Mr. Anthony Vitale Vice-President, Operations Entergy Nuclear Operations, Inc. Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530
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
SUBJECT: PALISADES NUCLEAR PLANT EVALUATION S OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000 255/2013007


==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. 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).
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.


Sincerely,/RA/ Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-255 License Nos. DPR-20  
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, Chie f Engineering Branch 3 Division of Reactor Safety Docket Nos.
 
50-255 License Nos. DPR-20  


===Enclosure:===
===Enclosure:===
Inspection Report 05000255/2013007
Inspection Report 05000255/201 3 00 7


===w/Attachment:===
===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  
Supplemental Information cc: Distribution via ListServ
Ž Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket No.:
50-255 License No.:
DPR-20 Report No.:
05000255/201 3 0 07 Licensee:
Entergy Nuclear Operations, Inc.
 
Facility:
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  


=SUMMARY=
=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.
IR 05000255/2013007, 01/07/2013  


===NRC-Identified===
- 01/24/2013
and Self-Revealed Findings B. No violations of significance were identified.
; 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.
 
N RC-Identified and Self-Revealed Findings B. No violations of significance were identified.


===Licensee-Identified Violations===
===Licensee-Identified Violations===
Line 47: Line 77:


=REPORT DETAILS=
=REPORT DETAILS=
Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity 1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
 
===Cornerstone:===
 
Initiating Events, Mitigating Systems, and Barrier Integrity 1R17 Evaluation s of Changes, Tests, or Experiments and Permanent Plant Modifications


===.1 ===
===.1 ===
{{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, 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
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 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
-plant walkdowns for portions of the modifie d 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.


===.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.===
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 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)==
This inspection constituted eight permanent plant modification samples as defined in IP 71111.17-04. b. No findings were identified.
 
Findings
 
==OTHER ACTIVITIES==
(OA)
{{a|4OA2}}
{{a|4OA2}}
==4OA2 ==
==4OA2 ==
===.1 Problem Identification and Resolution===
===.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
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 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
 
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
{{a|4OA6}}
{{a|4OA6}}
==4OA6 ==
==4OA6 ==
===.1 Meetings On January 24, 2013, the inspectors presented the inspection results to Mr. A. Vitale and other members of the licensee staff.===
===.1 Meetings O n January 24, 2013, the inspector===
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:   
 
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.
 
===Exit Meeting Summary===
ATTACHMENT:   


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL INFORMATION=


==KEY POINTS OF CONTACT==
Attachment
: [[contact::A. Vitale]], Site Vice-President Licensee  
SUPPLEMENTAL INFORMATION KEY POINTS OF CONTAC
: [[contact::A. Bono]], Design Engineer  
T
: [[contact::D. Fitzgibbon]], Design Engineering Manager  
: [[contact::A. Vitale]], Site Vice
-President Licensee  
: [[contact::A. Bono]], Design Engineer
: [[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 Assurance Director  
: [[contact::C. Arnone]], Nuclear Safety
: [[contact::C. Sherman]], Radiation Protection Manager  
Assurance Director
: [[contact::D. Kennedy]], Senior Engineer  
: [[contact::C. Sherman]], Radiation Protection Manager
: [[contact::G. Heisterman]], Maintenance Manager  
: [[contact::D. Kennedy]], Senior Engineer
: [[contact::M. Mlynarek]], Chemistry Manager  
: [[contact::G. Heisterman]], Maintenance Manager
: [[contact::N. Trela]], System Engineer  
: [[contact::M. Mlynarek]], Chemistry Manager
: [[contact::P. Russel]], Production Manager  
: [[contact::N. Trela]], System Engineer
: [[contact::T. Taylor]], Senior Resident Inspector, Palisades Nuclear Regulatory Commission
: [[contact::P. Russel]], Production Manager
==LIST OF ITEMS==
: [[contact::T. Taylor]], Senior Resident Inspector, Palisades
Nuclear Regulatory Commission
LIST OF ITEMS OPENED, CLOSED AND DISCUSS
ED NoneOpened, Closed, and Discussed


===OPENED, CLOSED AND DISCUSSED===
Attachment
NoneOpened, Closed, and  
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.
===Discussed===
CALCULATIONS
Number Description or Title
EA-ELEC-AMP-042 Date or Revision
Pressurizer
Heater Current Requirement
SUT1-2/SUT1-2/ALTC Startup Transformer1
-2 Load Tap Changer Automatic Controls
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
CR-PLP-2009-05236 EA-EC8350-04 Acceptance Criteria not Met
November 12, 2
009 CR-PLP-2010-05462 2400 Volts Bus 1
-C was Reading Low Out of Spec October 22, 2010
CR-PLP-2012-1775 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
A Schematic Diagram Turbine Control
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
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
2-0402 EC 27518 - Motor Control Center Buckets Replacement
December 18, 2012
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
10-0520 Revise FSAR Description of the Loss of Load Reactor Trip
10-0528 Fast Transfer Test
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  
Attachment
==LIST OF DOCUMENTS REVIEWED==
CFR 50.59 SCREENINGS
The following is a list of documents reviewed during the inspection.
Number Description or Title
: 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.
11-203 Date or Revision
: 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.
Replace Control Room Subcooling Recorder April 27, 2011
: CALCULATIONS Number Description or Title
2-0081 EC 34615 - Establish Pickup Setting for Relays 305L and 305
: EA-ELEC-AMP-042 Date or Revision Pressurizer Heater Current Requirement 0
-R March 1, 2012
: SUT1-2/SUT1-2/ALTC Startup Transformer1-2 Load Tap Changer Automatic Controls 1
MODIFICATIONS
: 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
Number Description or Title
: CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED Number Description or Title
EC 08005 Date or Revision
: CR-PAL-97-0355 Date or Revision Procedural Guidance for Opening
Replacement of 2400 SWGR Cubicle
: CV-3070/3071 HPSI Sub Cooling Valves March 11, 1997
EC 13204 Second Level Voltage Relay
: CR-PLP-2007-04259 Issues Related to EDG Fuel Oil Tank Volume Calculations September 21, 2007
EC 16993 Correct Level Settings for Diesel Fuel Oil Storage Tank T
: CR-PLP-2008-01392 MOC Switch Bayonet Operator With Broken Welds. March 26, 2008
-10a April 14, 2010
: CR-PLP-2008-01496 Diesel Fuel Oil Storage Tank T-10A Level Indication Dimension Discrepancy April 1, 2008
EC 5885 Emergency Diesel Generator 1
: CR-PLP-2009-03982 50.59 Evaluation for EC8350 did not Properly Address Question 2 August 19, 2009
-1 and 1-2 Starting Air System Reliability Upgrades
: CR-PLP-2009-04881 Formatting of a Particular Operations Procedure is Prone to Human October 21, 2009
EC 6432 Palisades Emergency Diesel Generator Diesel Fuel Oil Storage Requirements
: CR-PLP-2009-05236
EC 25561 Startup Transformer 1  
: EA-EC8350-04 Acceptance Criteria not Met November 12, 2009
- 2 Setpoint Change
: CR-PLP-2010-05462 2400 Volts Bus 1-C was Reading Low Out of Spec October 22, 2010
October 25, 2010
: CR-PLP-2012-1775
PROCEDURES
: PI-1490, K6B Starting Air Pressure Indicator for the Emergency Diesel Generator 1-2, was Reading Abnormally High March 19, 2012
Number Description or Title
: 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 
ESSO-14 Date or Revision
: 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
Flush HPSI Sub
: 10
-cooling Valves
: CFR 50.59 EVALUATIONS Number Description or Title 09-0601 Date or Revision Core operating Limits Report (COLR) January 19, 2010 09-0602
SOP-3 Safety Injection and Shutdown Cooling System 89 SOP-16 Component Cooling Water System
: EC 8350 - Replace Containment Spray Isolation Valves per
ESSO-1 Containment Spray Header Fill
: 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
Attachment
: EC 27518 - Motor Control Center Buckets Replacement December 18, 2012
LIST OF ACRONYMS USE
: 10
D ADAMS Agencywide Documents Access and Management System
: CFR 50.59 SCREENINGS Number Description or Title 09-0687 Date or Revision Modify
AR Action Report
: EX-10 0 10-0053 Technical Specifications Basis B-3.8.1 February 11, 2010 10-0065
ASME American Society of Mechanical Engineers
: ESSO-1, Containment Spray Header Fill February 17, 2010 10-0077
CFR Code of Federal Regulations
: 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
CNO Chief Nuclear Officer
: SOP-16, Component Cooling Water System October 22, 2010 11-0326 License Basis Document Change Request 10-013 August 18, 2011 
DRS Division of Reactor Safety
: Attachment 10
EC Engineering Change
: CFR 50.59 SCREENINGS Number Description or Title 11-203 Date or Revision Replace Control Room Subcooling Recorder April 27, 2011 12-0081
FIN Finding HPSI High Pressure Safety Injection
: EC 34615 - Establish Pickup Setting for Relays 305L and 305-R March 1, 2012
IMC Inspection Manual Chapter
: MODIFICATIONS Number Description or Title
MOV Motor-Operated Valve
: EC 08005 Date or Revision Replacement of 2400 SWGR Cubicle
NEI Nuclear Energy Institute
: EC 13204 Second
NRC U.S. Nuclear Regulatory Commission
: Level Voltage Relay 0
PARS Public Available Records System
: EC 16993 Correct Level Settings for Diesel Fuel Oil Storage Tank T-10a April 14, 2010
SPAR Standardized Plant Analysis Risk
: EC 5885 Emergency Diesel Generator 1-1 and 1-2 Starting Air System Reliability Upgrades 0
SSC Structures, Systems and Components
: EC 6432 Palisades Emergency Diesel Generator Diesel Fuel Oil Storage Requirements 1
TS Technical Specification
: 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]] [[]]
: [[ADAMS]] [[Agencywide Documents Access and Management System]]
: [[AR]] [[Action Report]]
: [[ASME]] [[American Society of Mechanical Engineers]]
: [[CFR]] [[Code of Federal Regulations]]
: [[CNO]] [[Chief Nuclear Officer]]
: [[DRS]] [[Division of Reactor Safety]]
: [[EC]] [[Engineering Change]]
: [[FIN]] [[Finding]]
: [[HPSI]] [[High Pressure Safety Injection]]
: [[IMC]] [[Inspection Manual Chapter]]
: [[MOV]] [[Motor-Operated Valve]]
: [[NEI]] [[Nuclear Energy Institute]]
: [[NRC]] [[]]
: [[U.S.]] [[Nuclear Regulatory Commission]]
: [[PARS]] [[Public Available Records System]]
: [[SPAR]] [[Standardized Plant Analysis Risk]]
: [[SSC]] [[Structures, Systems and Components]]
: [[TS]] [[Technical Specification]]
UFSAR Updated Final Safety Analysis Report
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,
Mr. Anthony Vitale
: [[MI]] [[49043-9530]]
Vice-President, Operations
: [[SUBJEC]] [[T: PALISADES NUCLEAR]]
Entergy Nuclear Operations, Inc.
: [[PLANT]] [[]]
Palisades Nuclear Plant
: [[EVALUA]] [[TIONS]]
27780 Blue Star Memorial Highway
: [[OF]] [[]]
Covert, MI 49043
: [[CHANGE]] [[S, TESTS,]]
-9530 SUBJECT: PALISADES NUCLEAR PLANT EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000255/2013007
: [[OR]] [[]]
Dear Mr. Vitale:
: [[EXPERI]] [[MENTS]]
On January 24, 2013, the  
: [[AND]] [[]]
: [[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
: [[PERMAN]] [[ENT]]
January 24, 2013, with you and other members of your
: [[PLANT]] [[]]
staff. The inspection examined activities conducted under your license as they relate to safety and compliance
: [[MODIFI]] [[CATIONS BASELINE INSPECTION]]
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.
: [[REPORT]] [[05000255/2013007 Dear Mr. Vitale: On January 24, 2013, the U.S. Nuclear Regulatory Commission (]]
No findings were identified during this inspection.
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
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
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
-rm/adams.html
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
(the Public Electronic Reading Room).
: [[10 CFR]] [[2.390 of the]]
Sincerely,   
: [[NRC]] [['s "Rules of Practice," a copy of this letter, its enclosure, will be available electronically for public inspection in the]]
/RA/  Robert  
: [[NRC]] [[Public Document Room or from the Publicly Available Records System (]]
: [[contact::C. Daley]], Chief
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,   
Engineering Branch 3
/RA/  Robert
Division of Reactor Safety
: [[C.]] [[Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-255 License Nos.]]
Docket Nos. 50
: [[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]]
-255 License Nos. DPR
: [[007 MOD]] [[50 59]]
-20 Enclosure:
: [[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]]
Inspection Report 05000255/201
: [[OFFICE]] [[]]
00 7   w/Attachment:  Supplemental Information
: [[RIII]] [[]]
cc: Distribution via ListServŽ
: [[RIII]] [[]]
DISTRIBUTIONSee next page
: [[RIII]] [[]]
: DOCUMENT NAME:
: [[RIII]] [[]]
G:\DRSIII\DRS\Work in Progress
: [[NAME]] [[ADahbur:ls RCDaley]]
\-PAL 2013 007
: [[DATE]] [[02/04/13 02/04/13]]
MOD 50 59 AKD.docx
: [[OFFICI]] [[AL]]
Publicly Available
: [[RECORD]] [[]]
Non-Publicly Available
: [[COPY]] [[Letter to Mr. Mr. Anthony Vitale from Mr. Robert]]
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
: [[C.]] [[Daley dated February 4, 2013.]]
OFFICE RIII RIII RIII RIII NAME ADahbur:ls
: [[SUBJEC]] [[T: PALISADES NUCLEAR]]
RCDaley   DATE 02/04/13 02/04/13   OFFICIAL RECORD COPY
: [[PLANT]] [[]]
Letter to Mr. Mr. Anthony Vitale
: [[EVALUA]] [[TIONS]]
from Mr. Robert C. Daley
: [[OF]] [[]]
dated February 4, 2013. SUBJECT: PALISADES NUCLEAR PLANT EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT
: [[CHANGE]] [[S, TESTS,]]
05000 255/2013007 DISTRIBUTIONJohn Cassidy
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: [[MODIFI]] [[CATIONS BASELINE INSPECTION]]
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: [[REPORT]] [[05000255/2013007]]
Steven Orth
: [[DISTRI]] [[BUTIONJohn Cassidy : RidsNrrPMPalisades Resource RidsNrrDorlLpl3-1 Resource RidsNrrDirsIrib Resource Chuck Casto Cynthia Pederson Steven Orth Allan Barker Christine Lipa Carole Ariano Linda Linn]]
Allan Barker
: [[DRPIII]] [[]]
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: [[DRSIII]] [[Tammy Tomczak ROPreports.Resource@nrc.gov]]
Carole Ariano
Linda Linn
DRPIII DRSIII Tammy Tomczak
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}}
}}

Revision as of 05:39, 19 July 2018

IR 05000255-13-007, 01/07/2013 - 01/24/2013, Palisades Nuclear Plant; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
ML13036A150
Person / Time
Site: Palisades Entergy icon.png
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)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532

-4352 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 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.

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, Chie f Engineering Branch 3 Division of Reactor Safety Docket Nos.

50-255 License Nos. DPR-20

Enclosure:

Inspection Report 05000255/201 3 00 7

w/Attachment:

Supplemental Information cc: Distribution via ListServ

Ž Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket No.:

50-255 License No.:

DPR-20 Report No.:

05000255/201 3 0 07 Licensee:

Entergy Nuclear Operations, Inc.

Facility:

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

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.

N RC-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 Evaluation s of Changes, Tests, or Experiments and Permanent Plant Modifications

.1

Main article: IP 71111.17

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 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

-plant walkdowns for portions of the modifie d 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 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

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 O n January 24, 2013, the inspector

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.

Exit Meeting Summary

ATTACHMENT:

SUPPLEMENTAL INFORMATION

Attachment

SUPPLEMENTAL INFORMATION KEY POINTS OF CONTAC

T

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 DISCUSS

ED 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

SUT1-2/SUT1-2/ALTC Startup Transformer1

-2 Load Tap Changer Automatic Controls

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

CR-PLP-2009-05236 EA-EC8350-04 Acceptance Criteria not Met

November 12, 2

009 CR-PLP-2010-05462 2400 Volts Bus 1

-C was Reading Low Out of Spec October 22, 2010

CR-PLP-2012-1775 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

A Schematic Diagram Turbine Control

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

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

2-0402 EC 27518 - Motor Control Center Buckets Replacement

December 18, 2012

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

10-0520 Revise FSAR Description of the Loss of Load Reactor Trip

10-0528 Fast Transfer Test

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

CFR 50.59 SCREENINGS

Number Description or Title

11-203 Date or Revision

Replace Control Room Subcooling Recorder April 27, 2011

2-0081 EC 34615 - Establish Pickup Setting for Relays 305L and 305

-R March 1, 2012

MODIFICATIONS

Number Description or Title

EC 08005 Date or Revision

Replacement of 2400 SWGR Cubicle

EC 13204 Second Level Voltage Relay

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

EC 6432 Palisades Emergency Diesel Generator Diesel Fuel Oil Storage Requirements

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

SOP-3 Safety Injection and Shutdown Cooling System 89 SOP-16 Component Cooling Water System

ESSO-1 Containment Spray Header Fill

Attachment

LIST OF ACRONYMS USE

D ADAMS Agencywide Documents Access and Management System

AR Action Report

ASME American Society of Mechanical Engineers

CFR Code of Federal Regulations

CNO Chief Nuclear Officer

DRS Division of Reactor Safety

EC Engineering Change

FIN Finding HPSI High Pressure Safety Injection

IMC Inspection Manual Chapter

MOV Motor-Operated Valve

NEI Nuclear Energy Institute

NRC U.S. Nuclear Regulatory Commission

PARS Public Available Records System

SPAR Standardized Plant Analysis Risk

SSC Structures, Systems and Components

TS Technical Specification

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, 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 05000255/201

00 7 w/Attachment: Supplemental Information

cc: Distribution via ListServŽ

DISTRIBUTIONSee next page

DOCUMENT NAME:

G:\DRSIII\DRS\Work in Progress

\-PAL 2013 007

MOD 50 59 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

OFFICE RIII RIII RIII RIII NAME ADahbur:ls

RCDaley DATE 02/04/13 02/04/13 OFFICIAL RECORD COPY

Letter to Mr. Mr. Anthony Vitale

from Mr. Robert C. Daley

dated February 4, 2013. SUBJECT: PALISADES NUCLEAR PLANT EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT

05000 255/2013007 DISTRIBUTIONJohn Cassidy

RidsNrrPMPalisades Resource

RidsNrrDorlLpl3

-1 Resource

RidsNrrDirsIrib Resource

Chuck Casto

Cynthia Pederson

Steven Orth

Allan Barker

Christine Lipa

Carole Ariano

Linda Linn

DRPIII DRSIII Tammy Tomczak

ROPreports.Resource@nrc.gov

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