IR 05000331/2010008

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June 17, 2010

Mr. Christopher Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785

SUBJECT: NEXTERA ENERGY DUANE ARNOLD, LLC, NRC TRIENNIAL HEAT SINK PERFORMANCE INSPECTION AND MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS TEMPORARY INSPECTION REPORT 05000331/2010008

Dear Mr. Costanzo:

On June 9, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed a triennial heat sink performance inspection and a managing gas accumulation in emergency core cooling, decay heat removal, and containment spray systems temporary inspection at your NextEra Energy Duane Arnold, LLC. The enclosed report documents the inspection results, which were discussed on June 9, 2010, with Mr. Kleinheinz 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. Based on the results of these inspections, three NRC-identified findings of very-low-safety significance were identified. The findings involved violations of NRC requirements. However, because of their very-low-safety significance, and because the issues were entered into your corrective action program, the NRC is treating the issues as Non-Cited Violations (NCVs) in accordance with Section VI.A.1 of the NRC Enforcement Policy. If you contest the subject or severity of this NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission - Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector Office at the NextEra Energy Duane Arnold, LLC. In addition, if you disagree with the characterization of any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region III, and the NRC Resident Inspector at the NextEra Energy Duane Arnold, LLC. The information that you provide will be considered in accordance with Inspection Manual Chapter 0305. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), 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/

Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 50-331;72-032 License No. DPR-49

Enclosure:

Inspection Report 05000331/2010008

w/Attachment:

Supplemental Information cc w/encl: Distribution via ListServ U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 05000-331 License No: DPR-49 Report No: 05000331/2010008 Licensee: NextEra Energy Facility: NextEra Energy Duane Arnold, LLC Location: Palo, IA Dates: March 8 through June 9, 2010 Inspectors: N. J. Féliz Adorno, Reactor Engineer, G. F. O'Dwyer, Reactor Engineer Approved by: Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor SafetyEnclosure i

SUMMARY OF FINDINGS

........................................................................................................... 1

REPORT DETAILS

REACTOR SAFETY

........................................................................................... 31R07Heat Sink Performance (71111.07T)

OTHER ACTIVITIES

.......................................................................................... 84OA5Other Activities ..................................................................................... 84OA6 Management Meetings ...................................................................... 13

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

K. Kleinheinz, Engineering Director
S. Catron, Licensing Manager
B. Murrell, Licensing Engineer Analyst
P. Collingsworth, System Engineer Nuclear Regulatory Commission
K. O'Brien, Deputy Division Director, Division of Reactor Safety
D. Hills, Chief, Engineering Branch 1
P. Lougheed, Acting Chief, Engineering Branch 2
A. M. Stone, Chief, Engineering Branch 2

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened

05000331/2010008-01 NCV Failure to evaluate the past operability of the 'B' control building chiller condenser
05000331/2010008-02 NCV Failure to update the UFSAR to reflect required cooling to the RHR pump seals
05000331/2010008-03 NCV Failure to ensure the operability of LPCI in Mode 3

Closed

05000331/FIN-2010008-01 NCV Failure to evaluate the past operability of the 'B' control building chiller condenser
05000331/FIN-2010008-02 NCV Failure to update the UFSAR to reflect required cooling to the RHR pump seals
05000331/FIN-2010008-03 NCV Failure to ensure the operability of LPCI in Mode 3 TI 2515/177 TI Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems

(NRC Generic Letter 2008-01) Discussed None1 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. 1R07 Heat Sink Performance (71111.07T) STP 3.7.5-01B; Quarterly Surveillance Test for "B" Control Building Chiller Operability; 1/9/2010 STP 3.7.5-01B; Quarterly Surveillance Test for "B" Control Building Chiller Operability; 10/9/2009 STP 3.7.5-01B; Biannual Surveillance Test for "B" Control Building Chiller Operability; 7/9/2008 STP NS540002; Emergency Service Water Operability Test; 2/3/2010
CAP 066572; A Chiller Will Not Remain Running More Than 3-5 Min after Start; 4/16/2009
CAP 063302; Chiller Placed In 50.65(A)(1) Maintenance Rule RED; 1/29/2009
CAP 061115; B Chiller Tripped With No Alarm in the Control Room; 10/21/2008
CAP051235; CAQ - Loose Material in Lower RHRSW Pump Motor Air Flow Area, 7/20/2007 CAP061471; CAQ - B SBDG Jacket Water HX Leaked 100 Dpm; 11/2/2008
CAP062296; NCAQ - ESW Flange Leak from Scavenging Air Cooler; 12/12/2008
CAP062658; RHRSW Pump Motor Windings PI Results Were Not Sat; 1/5/2009
CAP072204; NCAQ - ESW Leak from B JWHX; 1/7/2010
CAP062296; NCAQ - ESW Flange Leak from Scavenging Air Cooler; 12/12/2008
CAL-466-M007; Chiller Performance; 9/21/1990
CAL-466-M-003; ESW Heat Loads; 9/24/2007
WO1141621; Heat Exchanger Bio/Silt Fouling Inspection Form; 4/13/2009
WO1126573, Heat Exchanger Bio/Silt Fouling Inspection Form; 1/24/2005
WO1137879; Calibration Data Sheet: TC6924B; 5/21/2007
WO1145232; Calibration Data Sheet: PI6932B; 4/15/2009
WO1137870; Calibration Data Sheet: PI6932B; 5/20/2007
WO1145410; Calibration Data Sheet: TC6924B; 10/05/2009
PWO 1147549; Inspect and Clean A Intake Structure Pit Completed; 9/15/2009
PWO 1147554; Inspect and Clean A RHRSW/ESW Pit Completed; 9/11/2009
PWO 1147557; Inspect/Clean River Side of Intake Structure Pits Completed; 9/11/2009 2 Attachment
PWO 1147574, Inspect/Clean Pumphouse Stilling Basin Completed; 9/1/2009
PWO 1147569; Inspect and No Cleaning Needed B RHRSW and ESW Pits Completed; 9/2/2009
PWO 1147564; Inspect and No Cleaning Needed B Intake Structure Pit Completed; 8/21/2009
PWO 1147561; Inspect and No Cleaning Needed B Intake Structure Pit Completed; 6/2/2009
PWO 1147566; Inspect and Clean B RHRSW and ESW Pit Voided; 6/2/2009
PWO 1147571; Inspect and No Cleaning Needed and No Growth Pumphouse Stilling Basin Completed; 6/1/2009
PWO 114570; Inspect and No Cleaning Needed Pumphouse Stilling Basin Completed; 4/7/2009 NMC47-DAEC-02, Control Building Chiller B 1E235B; 1E236B; 1E237B; 1/26/2005
SE-99-041; 10
CFR 50.59 Safety Evaluation to Remove The Requirement For ESW Flow To The RHR Pump Seal Water Coolers From The TS Bases And The FSAR; Revisions 0 and 1 4OA5 Other Activities
CAL-M03-006; Appendix R - RHR and CS Keep Fill Calculation; 11/13/2003.
CAL-M06-022; HPCI System Transient Thermal Hydraulic Analysis; 3/27/2007
WO1146485; GL2008-01, Perform Inspection of "A" CS Discharge Piping for High Point Areas And Potential Gas Accumulation Points; 2/2/2009
WO1146488; GL2008-01; Perform Inspection of "B" RHR Suction Piping for High Point Areas and Potential Gas Accumulation Points; 2/2/2009
WO1146490; GL2008-01, Perform Inspection of "B" RHR Discharge Piping for High Point Areas and Potential Gas Accumulation Points; 2/2/2009
WO1146430; Inspection of High Point Areas of HPCI Suction; 9/22/2008
WO1146431; Inspection of High Point Areas of HPCI Discharge; 9/22/2008
WO1146422; Inspection of High Point Areas of CS A Suction; 9/8/2008
WO1146425, Inspection of High Point Areas of CS B Discharge; 9/6/2008
STP 3.5.1-13; HPCI System Water Fill Test; Revision 6 STP 3.5.1-13; Monthly Surveillance - HPCI System Water Fill Test; 1/1/2010 STP 3.5.1-13; Monthly Surveillance - HPCI System Water Fill Test; 12/3/2009
STP 3.5.1-14A; Monthly Surveillance - A Core Spray System Water Fill Test; 12/22/2009
STP 3.5.1-14A; Monthly Surveillance - A Core Spray System Water Fill Test; 1/16/2010
STP 3.5.1-14B; Monthly Surveillance - B Core Spray System Water Fill Test; 12/17/2009
STP 3.5.1-14B; Monthly Surveillance - B Core Spray System Water Fill Test; 1/20/2010 STP 3.5.1-15; RHR System Water Fill Test; Revision 1 3 Attachment Attachment STP 3.5.1-15; Monthly Surveillance - RHR System Water Fill Test; 12/18/2009 STP 3.5.1-15; Monthly Surveillance - RHR System Water Fill Test; 1/22/2010
OI-149; Residual Heat Removal System; Revision 113
OI-151; Core Spray System; Revision 58
OI-152, High Pressure Coolant Injection System; Revision 95 CAP060038; Small Air Pocket Found Upstream of MO2137; 9/4/2008 CAP060106, Air Pocket Measured Upstream of CV2037; 9/8/2008
COM030103; Complete
GL 2008-01 Walkdowns Deferred to
RFO 21; 7/1/2008
COM032036; Track Commitment to Evaluate and Adopt the Industry TSTF Traveler; 9/22/2008 CAP073588; Design Review Checklist; 3/3/2010
CAP073580;
GL 2008-01 Procedural Enhancements; 3/3/2010
CAP026345; MO2010 Tripped on Thermal Overload; 3/24/2003
SA043604;
GL 2008-01/Self-Assessment for NRC Inspection In Accordance With NRC
TI 2515/177; 3/8/2010
BECH-M123; HPCI Water Side; Revision 43
ISO-EBB-005-01; HPCI Pump Discharge; Revision 2
ISO-HBB-008-01; HPCI Pump Suction; Revision 1
ISO-EBB-006-01; HPCI Minimum Recirculation Line; Revision 1 Corrective Action Program Documents Generated as A Result of the Inspections CAP074017; Enhance
OI-149 Cautions to Alert Operators about Potential Valve Thermal Binding; 3/23/2010 CAP074021; Screening 4202 Does Not Appear Adequate to Support PWR25605; 3/23/2010 CAP074083; CAQ - NRC Finding -
MO 2010 Pressure Locking; 3/25/2010 CAP073762; Tubes Found Plugged During 1/24/2005 Cleaning of CB Chiller Condenser Were Not Evaluated; 3/10/2010 CAP073747; Conflicting Parameters between ACP1208.4 and STP 3.7.5-01; 3/9/2010 CAP073821; Missing Jam Nuts for 1VHX031A&B; 3/11/2010 CAP073369; CAQ - V42-0012 Not Full Stroke Exercised as Required By ASME; 2/23/2010 CAP074081; RHR Pump Seal Water Cooler - NRC Finding; 3/25/2010

LIST OF ACRONYMS

USED [[]]
ASME American Society of Mechanical Engineers
CAP Corrective Action Program
CFR Code of Federal Regulations ESW Emergency Service Water
FS [[]]
AR Final Safety Analysis Report
HP [[]]
CI High Pressure Core Injection
IP Inspection Procedure
NCV Non-Cited Violation
NRC U.S. Nuclear Regulatory Commission
RHR Residual Heat Removal
RHR [[]]

SW Residual Heat Removal Service Water

SDP Significance Determination Process
TS Technical Specification

UFSAR Updated Final Safety Analysis Report URI Unresolved Item

WO Work Order 5 Attachment
C. Costanzo -2- In accordance with 10
CFR 2.390 of the
NRC 's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), 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 Enclosure: Inspection Report 05000331/2010008 w/Attachment: Supplemental Information cc w/encl: Distribution via ListServ]]