IR 05000255/2013007
| ML13036A150 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/04/2013 |
| From: | Robert Daley Engineering Branch 3 |
| To: | Vitale A Entergy Nuclear Operations |
| Alan Dahbur | |
| References | |
| IR-13-007 | |
| Download: ML13036A150 (13) | |
Text
February 4, 2013
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
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
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
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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
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