IR 05000315/2013008
| ML13144A174 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/23/2013 |
| From: | Stone A M NRC/RGN-III/DRS/EB2 |
| To: | Weber L Indiana Michigan Power Co |
| Michael Jones | |
| References | |
| IR-13-008 | |
| Download: ML13144A174 (15) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 May 23, 2013 Mr. Larry Weber Senior Vice President and
Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT: D. C. COOK NUCLEAR POWER PLANT, UNIT 1
, NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL INSPECTION REPORT 05000 315/20 13008
Dear Mr. Weber:
On April 12 , 2013 , the U. S. Nuclear Regulatory Commission (NRC) completed the outage segment of the Post
-Approval Site Inspection for License Renewal at your D. C. Cook Nuclear Power Plant, Unit 1. The enclosed report documents the inspection activities, which were discussed on April 12, 2013, with Mr. J. Gebbie and other members of your staff
. This inspection was an examination of activities conducted under your renewed license as the y
relate to the completion of commitments made during the renewed license application process and compliance with the Commission's rules and regulations and the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and representative records, observations of activities, and interviews with personnel. On the basis of the sample selected for review, there were no findings of significance identified during this inspection. The NRC staff did not identify any instances of incomplete commitments with respect to timeliness or adequacy.
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 Document Access and Management System (ADAMS). ADAMS is 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
-315 License No. DPR
-58
Enclosure:
Inspection Report 05000315/2013 008
w/Attachment:
Supplemental Information cc w/encl:
Distribution via ListServTM Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos:
050003 15 License Nos: DPR-58 Report No:
05000 3 1 5/20 13 008 Licensee: Indiana Michigan Power Company Facility: D. C. Cook Nuclear Power Plant, Unit 1 Location: Bridgman, MI Dates: April 1 - April 12, 2013 Inspectors:
M. Jones, Reactor Engineer (Lead)
E. Sanchez, Reactor Engineer Approved by:
Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor Safety Enclosure 1
SUMMARY OF FINDINGS
IR 05000 315/201 3 008; 04/01/13 - 04/12/2013; D. C. Cook Nuclear Power Plant, Unit 1; Post-Approval Site Inspection for License Renewal. The inspection was conducted by two regional based inspectors. No instances were noted of incomplete license renewal commitments with respect to timeliness or adequacy. No finding s were identified by the inspectors. The significance of inspection findings are indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, "Significance Determination Process," dated June 2, 2011.
Cross-cutting aspects are determined using IMC 0310, "Components Within the Cross-Cutting Areas," dated October 28, 2011.
All violations of NRC requirements are dispositioned in accordance with the NRC's Enforcement Policy dated June 7, 2012. 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. N RC-Identified and Self-Revealed Findings No findings were identified.
B. Licensee-Identified Violations
No violations were identified.
2
REPORT DETAILS
Summary of Plant Status
D. C. Cook Nuclear Power Plant, Unit 1 was in a refueling outage during the period of this inspection.
OTHER ACTIVITIES
4OA5 Other Activities
.1 Post-Approval Site
Inspection for License Renewal (Phase I)
- IP 71003
a. Inspection Scope
- (1) Review of Newly Identified Systems , Structures and Components (SSC s) The inspectors discussed the identification of new SSCs, under the purview of Title 10 of the Code of Federal Regulations (CFR) 54.37(b), with the licensee's license renewal staff. No new SSCs were reviewed during Phase I of IP 71003 License Renewal Program Inspection.
Any new SSCs that are identified will be discussed and reviewed during the Phase II portion of IP 71003.
- (2) Review of Revised Commitments As part of reviewing the Aging Management Programs (AMPs) associated with the commitments, the inspectors identified the licensee performed a number of commitment revisions related to license renewal. These commitment changes and any others that may be generated will be reviewed during the Phase II portion of IP 71003.
- (3) Review of Commitments The inspectors reviewed supporting documents including completed surveillance records, conducted interviews, observed non
-destructive examination (NDE) activities, performed visual inspection of structures and components, including those not accessible during power operation, and observed the activities described below to verity the licensee completed the necessary actions to comply with the license conditions that are a part of the renewed operating license. The inspectors verified the licensee implemented the "outage related" aging management programs included in NUREG
-1831 , "Safety Evaluation Report (SER) Related to the License Renewal (LR) of the Donald C. Cook Nuclear Plant, Unit 1 and Unit 2
," in accordance with 10 CFR Part 54, "Requirements for the Renewal of Operating Licenses for Nuclear Power Plants."
b. Results of Detailed Reviews The inspectors reviewed portions of the commitments below
, which are listed by Aging Management Program number and referenced to Commitment Item number from Appendix A of the SER. Activities observed related to these commitments are also listed. Specific documents reviewed are listed in the
.
3 (1) (B.1.4) Boric Acid Corrosion Program (Commitment Item 4)
The Boric Acid Corrosion Program is an existing program that is consistent with NUREG-1801 , "Generic Aging Lessons Learned (GALL) Report," July 2001,Section XI.M10, Boric Acid Corrosion, with an enhancement. The program manages aging effects for structures and components, and supports as a result of borated water leakage. The program requires periodic visual inspection of adjacent structures, components, and supports for evidence of leakage and corrosion. The program includes provisions for:
- (a) determination of principal location of leakage,
- (b) examination requirements and procedures for locating small leaks, and
- (c) engineering evaluations and corrective actions to ensure that boric acid corrosion does not lead to degradation at the leakage source or adjacent structures or components. This program complies with the requirements of NRC Generic Letter 88
-05, "Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants." Commitment Item 4 states "the following enhancements to the Boric Acid Corrosion Prevention Program will be implemented prior to the period of extended operation:
- (a) the program scope will be revised to address electrical components in addition to ferrite steel, and
- (b) the program acceptance criteria will be revised to address electrical components in addition to ferrite steel."
The inspectors reviewed the procedures and documentation related to the Boric Acid Corrosion Control Program. The inspectors also reviewed a sample of corrective action records from the previous and current refueling outages pertaining to identified boric acid leakage or buildup, and the boric acid corrosion evaluations associated with these identified boric acid leaks/deposits. In addition, the inspectors performed a walkdown of containment to identify boric acid leaks and confirm they had been identified by the licensee and entered into their Corrective Action Program. The inspectors had no concerns with the observed and reviewed activities.
(2) (B.1.6) Buried Pipe Inspection Program (Commitment Item s 5, and 42) The Buried Pipe Inspection Program is consistent with, but includes an exception to, the program described in NUREG
-1801, July 2001,Section XI.M34, "Buried Pipe Inspection Program." The program manages the loss of material caused by corrosion of the external surface of buried carbon steel piping and tanks. The Buried Pipe Inspection Program includes
- (a) preventive measures to mitigate corrosion, and
- (b) periodic inspections to manage the effects of corrosion on the pressure retaining capability of buried carbon steel piping and tanks.
Commitment Item 5 states "the buried Piping Inspection Program will be implemented prior to the period of extended operation." Commitment Item 42 states, in response to an Advisory Committee on Reactor Safety License Renewal Subcommittee comment regarding scheduling of buried piping inspections, the licensee "commits to enhance the new Buried Piping Inspection Program to require performance of an inspection of a sample of buried piping included in the scope of this program within ten years after entering the period of extended operation, unless an opportunistic inspection of similar underground piping has occurred within this ten
-year period.
Before the end of the tenth year of extended operation, I&M [the licensee] will perform an engineering evaluation to determine if sufficient inspections have been conducted to draw a conclusion regarding the ability of the underground coatings to protect the underground piping from 4 degradation.
If not, I&M will conduct an inspection of a sample of buried piping to allow that conclusion to be reached.
" The inspectors conducted interviews, reviewed program, work, and implementing documents. The inspectors had no concerns with the observed activities.
(3) (B.1.13) Heat Exchanger Monitoring Program (Commitment Item 9)
The Heat Exchanger Monitoring Program is new plant specific program. The program is credited with inspecting the heat exchangers for age related degradation that includes loss of material and cracking of the tubes.
The heat exchanger Monitoring Program includes provisions to:
- (1) develop testing techniques based on industry operating experience
- (2) determine the sample population of heat exchangers based on operating experience before the inspections
- and
- (3) perform an eddy current inspection of the tubes every 10 years, or more frequently if inspection results indicate a need for more frequent inspections.
Commitment Item 9 states "the Heat Exchanger Monitoring Program will be initiated prior to the period of extended operation."
The inspectors observed eddy current testing performed under work order (WO) 55395252;"1
-HE-15W, Perform Inspection of Heat Exchanger (Generic Letter 89-13)" for the component cooling water (CCW) heat exchanger.
In addition, inspectors reviewed heat exchanger test data associated with past eddy current testing performed on the Unit 1 East and West CCW heat exchanger tubes, Unit 1 emergency diesel generator (EDG) jacket water cooler (1
-QT-131-AB), and Unit 1 EDG lube oil cooler (1-QT-110-AB). The inspectors conducted interviews with plant personnel, and reviewed work orders and procedures associated with the heat exchanger monitoring program. The inspectors had no concerns with the observed activities
. (4) (B.1.18) Inservice Inspection - American Society of Mechanical Engineers (ASME)Section XI, Augmented Inspections (Commitment Item 10) The Inservice Inspection
- ASME Section XI, Augmented Inspections Program is an existing plant specific program. The program manages the effects of aging on selected components outside the jurisdiction of ASME Section XI. The program description states "Augmented Inspection shall be consistent, to the extent practical, with the appropriate ASME requirements of ASME Section XI (i.e.
, selection of inspection methods, inspection frequency, percentage of components examined within a population, and acceptance criteria)." The program is implemented in accordance with the applicable requirements of the 1989 Edition of ASME Section XI, approved NRC alternatives and relief requests, and other requirements specified in 10 CFR 50.55a for the third ISI interval
. Commitment Item 10 states "the following enhancements to the Inservice Inspection (ISI) - ASME Section XI, Augmented Inspections Program will be implemented prior to the period of extended operation:
- (a) An augmented ISI volumetric inspection of the spray additive tanks (SATs) and the portions of the containment spray system that are wetted by sodium hydroxide
- (b) An augmented ISI volumetric inspection of the portions of the discharge header in containment that may contain water with concentrated contaminants."
5 The inspectors reviewed procedures and documentation related to the augmented ISI program. The inspectors also observed UT examinations on two weld s in a containment spray line conducted under WO 55365371
-06. The inspectors had no concerns with the observed and reviewed activities.
(5) (B.1.19) Instrument Air Monitoring Program (Commitment Item 11)
The Instrument Air Monitoring Program is an existing plant specific program. The Instrument Air Quality Program is credited with preventing and mitigating aging effects on control air system components by maintaining the system free of water and significant contaminants. The program
's requirements were derived from, and are consistent with, the guidelines presented in American National Standards Institute (ANSI) ISA-S7.3-1975, "Quality Standards for Instrument Air." The aging effects are managed through periodic monitoring of
- (1) maximum dew point (monitored approximately weekly)
- (2) particulate size (after
-filter differential pressure monitored daily); and
- (3) dryer condition inspection (monitored approximately monthly).
Commitment Item 11 states the licensee will "enhance the program procedure prior to the period of extended operation to clearly specify frequencies for the dew point and dryer tours.
" The inspectors conducted interviews, reviewed implementing documents, work orders, and procedures. The inspectors verified procedural enhancements were performed to incorporate frequencies for dew point monitoring and dryer tours. The inspectors had no concerns with the updated and revised documentation.
(6) (B.1.22) Non
-Environmental Qualified (EQ) Insulated Cables and Connections (Commitment Item 14)
The Non-EQ Insulated Cables and Connections Program is a new program that is consistent with NUREG
-1801, July 2001,Section XI.E1, "Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements."
The Non-EQ Insulated Cables and Connections program will detect aging effects for accessible insulated cables caused by heat, radiation and moisture prior to loss of intended function. The aging effects are managed through visual inspection of representative samples of accessible insulated electrical cables and connections at a frequency of at least once every ten years.
Commitment Item 14 states "the Non-EQ Insulated Cables and Connections Program will be implemented prior to the period of extended operati on." The inspectors conducted interviews, observed visual inspections during the performance of WO 55394233, "Inner Volume Quad 1,4 LWR Containment Cable Assessment", and reviewed additional program inspection results and documents. The inspectors had no concerns with the observed activities.
(7) (B.1.30) Small Bore Piping One Time Inspection Program (Commitment Item 22)
The Small Bore Piping Program is new program that will be consistent with NUREG
-1801, July 2001,Section XI.M32, "One Time Inspection."
The program is credited for managing the cracking of small bore Class 1 piping (< 4 inch nominal pipe size), including pipe, fittings, and branch connections, in the reactor coolant systems. The 6 Small Bore Pipe Program includes provisions to perform one
-time volumetric inspections on risk-informed locations susceptible to cracking.
Commitment Item 22 states "the Small Bore Piping Program will be implemented prior to the period of extended operation."
The inspectors reviewed inspection records of small bore piping, conducted interviews, and reviewed program scoping documentation. The inspectors had no concerns with the reviewed documentation
. (8) (B.1.39) Wall Thinning Monitoring Program (Commitment Item 28
) The Wall Thinning and Monitoring Program is a new plant specific program.
The program is credited for managing the aging effects for loss of material to ensure wall thickness is above the minimum required in order to avoid failures under normal, transient, and accident conditions, including seismic events.
The applicant stated inspections will be performed periodically, at a frequency to be determined before the end of the initial 40
-year licensing term.
Commitment Item 28 states the "Wall Thinning Monitoring Program" will be implemented prior to the period of extended operation.
The inspectors observed a wall thinning inspection performed under WO 55273928, "1-WCR-964 UT/Piping Downstream." The inspectors reviewed test results, reviewed program implementing documents, and conducted interviews with licensee staff. The inspectors had no concerns with the observed activities or documentation reviewed.
(9) (B.1.14) American Society of Mechanical Engineers (ASME) Code,Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (No Associated Commitment Item
) The ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD Program is an existing program that is consistent with NUREG
-1801, July 2001,Section XI.M1, "ASME Section XI, Subsections IWB, IWC and IWD." The program is implemented in accordance with the requirements of the 1989 Edition of ASME Section XI, approved NRC alternatives and relief requests, and other requirements specified in 10 CFR 50.55a for the third ISI interval. The ASME Section XI, Subsections IWB, IWC, and IWD Inservice Inspection Program manage cracking and loss of material through periodic visual, surface, and volumetric examination and leakage test of all Class 1, 2, and 3 pressure retaining components and their integral attachments.
The inspectors conducted interviews and reviewed documentation. The inspectors also observed NDE examinations related to the licensee's In-Service Inspection Program. These included ultrasonic examination (UT) of the 54 reactor pressure vessel studs performed under WO553 95571-01 and UT of the steam generator feedwater nozzle inner radius, performed under WO 55364385
-01. In addition, the inspectors observed NDE examinations as part of the RI
-ISI Program. This included risk
-informed UT examination of a Class 1 pressurizer surge line weld performed under WO 5535567-01. The inspectors had no concerns with the observed and reviewed activities.
4OA6 Management Meetings
.1 Exit Meeting Summary
On April 12, 2013, the inspectors presented the inspection results to Mr. J. Gebbie and other members of the licensee staff. The licensee acknowledged the issues presented.
The inspectors confirmed that none of the potential report input discussed was considered proprietary.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
Attachment
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTAC
T Licensee
- L. Weber, Senior Vice President and Chief Nuclear Officer
- J. Gebbie, Site Vice President
- J. Ross, Palnt Engineering Director
- S. Lies, Engineering Vice President
- T. Gottlieb, License Renewal/Supervisor
- M. White, Weld Program Owner
- K. Henderson, Regulatory Affairs
- S. Mitchell, Regulatory Affairs
LIST OF ITEMS OPENED, CLOSED AND DISCUSS
ED Opened, Closed and Discussed
None LIST OF DOCUMENTS REVIEWED The following is a partial list of documents reviewed during the inspection. Inclusion on this list does not imply that the NRC inspector reviewed the documents in their entirety, but rather that selected sections or 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.
Work Orders
- 55273928; NQQS, 1
-WCR-964, UT/Piping Downstream of 1
-WCR-964; dated April 9, 2013
- 55365731; EISI; Perform ISI Exams Downstream Welds for 1
-CTS-127E; dated September 7, 2012 - 55380958; 1
-QT-102-AB Inspect Expansion Joint; dated April 4, 2013
- 55394233; Eng Inner Vol. Quad 1,4 LWR Cntmt Cable Assess W/D; dated April 8, 2013
- 55395252; ENU, 1
-HE-15W, Perform Inspection of Heat Exchanger (89
-13);dated April 1, 2013 - 55395267; ENO, (PH
-1), 1-QT-110-AB, Perform Inspection of Cooler; dated April 1, 2013
- 55395567; EISI Vendor Exams on RCS Welds in U1; dated September 7, 2012
- 55395570; NQQS Perform Examination on RPV Flange Bolting Nuts; dated April 4, 2013
Attachment
- 55395571; EISI Vendor Exams on RPV During UIC2; dated September 7, 2012
- 55403347-28; 1-DG-04-2005 Underground Piping and Tank Integrity Program, Visual Inspection Data Sheet; dated November 16, 2012
- 5540 9565-03; 2-DG-04-1000 Underground Piping and Tank Integrity Program, Visual Inspection Data Sheet; dated November 7, 2012
- 55412937; 12
-THP-6040-PER-005; Control Air Dew Point Tour; dated October 31, 201
Procedures
- 12-EHP-5040-ICC-001; Non-Eq Insulated Cables and Connections Program Implementation; Revision 1
- 12-EHP-8913-001-002; Heat Exchanger Inspection; Revision 7
- 12-MHP-5021-001-154; Inspection of Rubber Expansion Joints; Revision 8
- 12-QHP-5050-NDE-006; Visual Examination:
VT-1 and VT-3; Revision 5
- 12-THP-6040-PER-005; Control Air Performance Monitoring; Revision 13
- EHI-5054-HXM; Heat Exchanger Monitoring; Revision 3
- LMT-04-UT-113; Ultrasonic Examination of Nozzle Inner Radius Areas; Revision 2
- PDI0UT-2; Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds; Revision F
- PDI-UT-11; Generic Procedure for the Detection and Sizing of Reactor Pressure Vessel Nozzle to Shell Welds and Nozzle Inner Radius; Revision B
- PDI-UT-5; Generic Procedure for Straight Beam Ultrasonic Examination of Bolts and Studs; Revision D
- PMP-5020-001-001; Maintenance Permits; Revision 30
- PMP-5030-001-001; Boric Acid Corrosion Control; Revision 16
- UT-95; Ultrasonic Examination of
Austenitic Piping Welds; Revision 7
- UT-97; Straight Beam Ultrasonic Examination of Bolts and Studs; Revision 4
Other - AEP10-DC1-1-HE-15E; Component Cooling Water Heat Exchanger 1-HE-15E; dated October 11, 2006 - AR 2011-10619; 2-TK-39-DN; Dew Point Greater Than 34 Degrees F; dated September 19, 2011 - AR 2011-10886; 1-CS-331 has 12 DPM Packing Leak Following Operation; September 24, 2011
Attachment
- AR 2011-11103; Reactor Vessel Upper Head Examination Results; September 28, 2011
- AR 2011-8350; 2-TK-39-DN Dew Point Not Meeting Acceptance Criteria; dated July 7, 2011
- AR 2012-9973; Active Boric Acid
Leak on Flange Upstream of 1
-QFR-30; August 15, 2012
- AR 2013-4648; 1-HE-15W GL 89-13 Inspection SAT; dated March 31, 2013
- AR 2013-4810; Fibrous Material Found in Cable Tray; April 2, 2014 - AR 2013-4927; U1 Containment, various boric acid leaks; April 4, 2013
- Calc No. 013001; FAC System Susceptibility Evaluation; Revision 0
- DIT-B-03483-00; Security Diesels Not
Credited for Outside Lighting For App. R or NFPA 805 Fire Protection Programs; dated January 26, 2012
- Drawing OP
-1-5151C-54; Flow Diagram Emergency Diesel Generator "CD" Unit 1; Revision 15 - GT 2011-3676; License Renewal Implementation (Y10) Small Bore Piping; January 31, 2012
- LR-MAMR-19; Aging Management Review of the Security Diesel; Revision 2
- LRP-MAMR-10; Aging Management Review of the Component Cooling Water System ; Revision 3
- LRP-MAMR-11; Aging Management Review of the Emergency Diesel Generator System; Revision 2
- U1-VE-13-001; Ultrasonic Examination; April 6, 2013
- U1-VE-13-006; Ultrasonic examination; April 6, 2013
- U1-VE-13-028; Ultrasonic Examination; April 5, 2012
- VT-06-076; Visual Examination of Reactor Vessel Internals; October 23, 2006
- VTD-GARK-0001; Garlock Installation
a nd Maintenance Manual for Expansion Joints; Revision 5
Attachment
LIST OF ACRONYMS USE
D ADAMS Agencywide Document Access Management System
AMP Aging Management Program
ASME American Society of Mechanical Engineers
CCW Component Cooling Water
CFR Code of Federal Regulations
EDG Emergency Diesel Generator
GALL Generic Aging Lessons Learned
IMC Inspection Manual Chapter
IP Inspection Procedure
IR Inspection Report
NDE Non-Destructive Examination
NEI Nuclear Energy Institute NRC U.S. Nuclear Regulatory Commission
PARS Publicly Available Records System
SDP Significance Determination Process
SER Safety Evaluation Report
SSCs Systems, Structures, and Components
UT Ultrasonic Testing
WO Work Order
L. Weber -2- of NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is 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
-315 License No. DPR
-58 Enclosure: Inspection Report 05000315/2013
008 w/Attachment: Supplemental Information
cc w/encl:
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