IR 05000315/2008008
| ML083380249 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/01/2008 |
| From: | Hills D E NRC/RGN-III/DRS/EB1 |
| To: | Rencheck M W Indiana Michigan Power Co, Nuclear Generation Group |
| References | |
| IR-08-008 | |
| Download: ML083380249 (17) | |
Text
December 1, 2008
Mr. Michael 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, UNITS 1 AND 2 EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000315/2008008(DRS); 05000316/2008008(DRS)
Dear Mr. Rencheck:
On October 30, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed the Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your D. C. Cook Nuclear Power Plant, Units 1 and 2. The enclosed report documents the inspection results, which were discussed on October 30, 2008, with Mr. Larry Weber 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 this inspection, no findings of significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and 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/ David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74
Enclosure:
Inspection Report 05000315/2008008(DRS); 5000316/2008008(DRS)
w/Attachment:
Supplemental Information cc w/encl: L. Weber, Site Vice President J. Gebbie, Plant Manager G. White, Michigan Public Service Commission Michigan Department of Environmental Quality Planning Manager, Emergency Management and Homeland Security Division, Michigan State Police Department T. Strong, State Liaison Officer
SUMMARY OF FINDINGS
IR 05000315/2008008(DRS); 05000316/2008008(DRS); 10/20/2008-10/30/2008; D. C. Cook Nuclear Power Plant, Units 1 and 2; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications. The inspection covered a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by three regional based engineering inspectors. Based on the results of this inspection, no findings of significance were identified. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter (IMC) 0609, "Significance Determination Process" (SDP). Findings for which the SDP does not apply may be Green or be assigned a severity level after NRC management review. 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. NRC-Identified
and Self-Revealed Findings
Cornerstone: Initiating Events
No findings of significance were identified.
Cornerstone: Mitigating Systems No findings of significance were identified. Cornerstone:
Barrier Integrity No findings of significance were identified.
B. Licensee-Identified Violations
No findings of significance were identified.
2
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
.1 Evaluations of Changes, Tests, or Experiments
a. Inspection Scope
From October 20, 2008, through October 30, 2008, the inspectors reviewed ten evaluations performed pursuant to 10 CFR 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 14 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. In regard to the changes reviewed where no 10 CFR 50.59 evaluation was performed, the inspectors verified that the changes did not meet the threshold to require a 10 CFR 50.59 evaluation. The evaluations and screenings were chosen based on risk significance, safety significance, and complexity. The documents reviewed are listed in the Attachment to this report. 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 constitutes ten samples of evaluations and 14 samples of changes screened out as defined in Inspection Procedure 71111.17.
b. Findings
No findings of significance were identified.
.2 Permanent Plant Modifications
a. Inspection Scope
From October 20, 2008, through October 30, 2008, the inspectors reviewed ten permanent plant modifications that had been installed in the plant during the last three years. The modifications were chosen based upon risk significance, safety significance, and complexity. The inspectors reviewed the modifications to verify that the completed design changes were in accordance with the specified design requirements, and the licensing bases, and to confirm that the changes did not adversely affect any systems' safety function. Design and post-modification testing aspects were verified to ensure the functionality of the modification, its associated system, and any support systems. The 3inspectors also verified that the modifications performed did not place the plant in an increased risk configuration. 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 in the Attachment to this report. This inspection constitutes ten samples as defined in Inspection Procedure 71111.17.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES (OA)
4OA2 Identification and Resolution of Problems
.1 Routine Review of Condition Reports
a. Inspection Scope
From October 20, 2008, through October 30, 2008, the inspectors reviewed 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 for changes, tests, or experiments issues. 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 corrective action system. The specific corrective action documents that were sampled and reviewed by the team are listed in the attachment to this report.
b. Findings
No findings of significance were identified.
4OA6 Management Meetings
.1 Exit Meeting Summary
On October 30, 2008, the inspectors presented the inspection results to Mr. Larry Weber 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
KEY POINTS OF CONTACT
Licensee
- L. Weber, Sr. Vice President
- J. Nimtz, Licensing Activity Coordinator
- J. Zwolinski, NRA Manager
- M. Scarpello, Licensing Manager
- S. Saad, Structural Supervisor
- S. Bischof, Principal Engineer
- P. VandeVisse, I&C Design Engineer
- A. Petrowsky, Director, Design Engineering
- A. Parihk, Principal Nuclear Specialist
- R. Neuendorf, Configuration Control Manager Nuclear Regulatory Commission
- J. Lennartz, Senior Resident Inspector
- P. LaFlamme, Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None
2
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 Date or Revision12-E-S-ELCP-4Kv-002 Bus Transfer Calculation
- 1-2-O1-02 Calc 1
- RTS/ESFAS Allowable Values and Associated Nominal Trip Setpoints for Extended Surveillance Intervals
- 1-E-N-ELCP-4KV-001-VOLT Unit 1 Voltage Adequacy Analysis
- 0
- PS-4KVP-009 4-kV RCP Bus Under-frequency Relay Settings 0
- MD-12-ESW-106-N Assessment of Increased Lake Water Temperature on Safety Related and Non-Safety Related Systems
- MD-12-RH-212-N Determination of Water Inertia Loads for Miscellaneous ECCS Valves
- MD-02-RH-022-N Analysis of Thrust and Torque Limits for
- MOV2-IMO-314 3
- IMO-314 & 324 3
- DC-D-02-CS-14 Piping and Pipe Support Analysis of the Chemical and Volume Control System from the RCP Cold Leg No. 4 to Regenerative Heat Exchanger and 2" Waste Disposal line to the Penetration Wall
- CPS-7
- SD-991014-001 Pipe Supports 2-GSI-V62 and 2-GSI-V61 for 10" SI overflow pipe
- SD-000429-020 Qualification of pipe supports for 10" SI overflow pipe
- SD-000502-004 Piping Stress Analysis and support load determination for the 10" overflow line off the
- 3CALCULATIONS
- Number Description or Title Date or RevisionRWST per
- DCP-1-DCP-678
- SD-990913-006 Piping Stress Analysis and support load determination for the 10" overflow line off the
- RWST per
- DCP-2-DCP-678
- MD-12-RWST-001-N Maximum Differential Pressure for RWST Vent Path 3
- DC-D-01-SI-2 Piping and Pipe Support Analysis of the Safety Injection System (SI)
- DC-D-02-RC-2306 Pipe Stress Analysis and Support Qualification for the RCS Mid-Loop Level Monitoring System Piping from the Pressurizer Relief Valve Discharge Line to Sight Glass
- NGG-100 and Instrument
- NLI-112
- DC-D-01-RC-5365 Piping and Pipe Support Analysis of the Pressurizer Safety Valve and the Power Operated Relief Valve
- Discharge Piping System from the Pressurizer to the Pressurizer Relief Tank
- SD-010321-001 Determine the Structural Adequacy of the Anchorage of the East and West Motor Driven Auxiliary Feedwater Pumps, the Turbine Driven Auxiliary Feedwater Pump, and the enclosure of the West Motor Driven Auxiliary Feedwater Pumps 0
- SD-060213-001 Piping and Support Structural Evaluation for Unit 1 Containment Recirculation Sump Vent Line in Support of Modification 1-MOD-65754
- SD-060307-001 Qualification of Mounting Details for Containment Recirculation Sump Level Switches for 1-MOD-65754
- DC-D-02-CCW-31
- LBPRP-Piping and Pipe Supports Analysis of the CCW Piping System
- DC-D-01-RH-01 Piping and Pipe Support Analysis of the RHR, SI, CTS and CVCS Piping from the RWST to Pumps 1-PP-050E/W (CCP), 1-PP-009E/W (CTS), 1-PP-049 (Reciprocating Charging), 1-
- PP-035E/W (RHR), 1-PP-026N/S (SI) and Containment Penetrations 1-CPN-16, 1 -CPN-45, 1-CPN-46, 1-CPN-47, 1-CPN-48, 1-CPN-49, 1-CPN-50 and 1-CPN-51 for the Large Bore Piping Reconstitution Program
- 4CORRECTIVE ACTION PROGRAM DOCUMENTS ISSUED DURING INSPECTION
- Number Description or Title Date or Revision
- AR 08295053 Admin Errors in Modification Package 10/22/2008
- AR 08298014 Insufficient Documentation in Modification Package
- 10/27/2008
- AR 08296062 Admin Errors in 50.59 Screening 10/22/2008
- IR 08301024 Typo-Discrepancy in analysis for calculation DC-D-02-CCW-
- 10/27/2008
- IR 08303072 Discrepancies - pipe support 1-ARH-R4011-Calc
- DC-D-01-RH-01
- 10/29/2008
- AR 08304007 Evaluate Fouling Factor / Margin on CTS
- HX 10/30/2008
- AR 08304014 Inspector Notes Piping Calculations Were Hard to Follow 10/30/2008
- AR 08304028 NRC Observations of HU Performance Issues During Mod/50.59 Inspection 10/30/2008
- CORRECTIVE ACTION PROGRAM DOCUMENTS ISSUED PRIOR TO INSPECTION
- Number Description or Title Date or Revision
- AR 00804005 Fuse Blown for Back Up Power to Load Changer for TR101CD 10/13/2006
- AR 00819295 Min Volt at Relay Should be Used Not Min Batt Volt in EC 9/21/2007
- CR 04175023 Single Point Vulnerability Analysis RCP Trip on Bus Under-frequency
- 06/23/2004
- AR 00840100 Loss of Configuration EDG Fuel Injection Pumps 10/10/08
- AR 00826854 Loss of Configuration EDG Fuel Injection Pumps 02/22/2008 ESAT
- 08284025 Loss of Configuration EDG Fuel Injection Pumps 10/13/2008 ESAT
- 08270024 Power supply not installed per RTO mod package EC-
- 47709 10/03/2008
- IR 00801589 Answer to 1
st two 50.59 Eval questions appear incorrect 8/15/06
- IR 00823302 Two detail errors were identified in
- AD 2006-0339-00 12/12/07
- DRAWINGS Number Description or Title Date or Revision
- OP-2-98050-24 Reserve Bus Tran. And Auxiliary Buses Low Voltage Protection Elem. Diagram
- OP-2-98041-31 4 KV Aux Transformers 2AB & 201AB Elementary Diagram 31
- OP-2-98045-35 4 KV/600 V Auxiliary Transformers 21A & 21C Elementary Diagram Sheet 1 of 2
- OP-2-98046-29 4
- KV 600 V Auxiliary Transformers 21B & 21D Elementary Diagram Sheet 1 of 2
- OP-2-12001-42 Main Auxiliary One-Line Diagram Bus "A" & "B" ESF Train
- B 42
- OP-2-12002-37 Main Auxiliary One-Line Diagram Bus "C" & "D" ESF Train
- A 37
- 5DRAWINGS Number Description or Title Date or Revision
- BOP 27
- OP-1-98002-3 Transformer 101 AB Temperature & Cooling Elementary Diagram 3
- OP-1-98003-2 Transformer 101 AB Load Tap Changer Motor Drive Control Elem Diagram
- OP-1-98002-
- E047420 Transformer 101 AB Temperature & Cooling Elementary Diagram 0
- OP-1-98004-2 Transformer 101 AB Load Tap Changer
- Control Elem Diagram 2
- 50.59 EVALUATIONS
- Number Description or Title Date or Revision
- 2007-0375-00 Loss of All AC Power
- 1/14/2008 2007-0200-00 Open RHR Cross-tie Modification 0 2008-0177-00 Implementation of New Recirculation Sump Design and Licensing Basis Requirements
- 2007-0142-01 Using VCT Pressure to Adjust #23 RCP No. 2 Seal Leakoff 2 2006-0325-00 Change Tech Spec Basis 3.7.9 to Increase UHS Temperature From 85.8 to 86.8 deg. F
- 2007-0210-01 Unit 2 Containment Sump Remote Strainer Modification 10/31/2007 2006-0224-00 Containment Sump Debris Accumulation Modifications 8/29/2006
- 2007-0422-00 Unit 1 Containment Sump Remote Strainer Modification 1/10/2008
- 2007-0104-00 Unit 2 Containment Sump Modification 5/2/2007 2007-0210-00 Unit 2 Containment Sump Remote Strainer Modification 9/10/2007
- 50.59 SCREENINGS
- Number Description or Title Date or Revision
- 2007-0371-00 Time Response and Verification of Engineered Safety Features 10/29/2007 2007-0039-00 Update FSAR Section 8.7.2.4 for CRID Temperatures 2/2/2007 2007-0172-00 Revise RAT LTC Control Power Transfer Schemes 8/29/2008 2007-0070-00 Compensatory Measure in Support of Control Room Habitability and Offsite Dose Analyses 3/2/2007 2007-0567-00 Unit 2 Degraded Voltage Back-Fit Modification
- 0 2008-0180-00 Modify SDG Auto-start Relay 5/9/2008 2008-0131-00 Change Unit 1 Design Basis ESW Flow to CTS HX 4/7/2008 2007-0339-00 SI Termination 1(2)
- OHP-4023-ES-1-1 Rev 17/16 10/11/2007
- 2007-0252-00 Malfunction of a Reactor Coolant Pump 8/10/2007
- 650.59 SCREENINGS
- Number Description or Title Date or Revision
- 2008-0025-00 Revision 5 of
- EHI-5300 is Removing Requirement to LLRT
- CPN-45 and 46 1/23/2008 2008-0240-00 Change of Setpoint for 2-CFA-454 Low Flow 7/2/2008 2007-0402-00 Change Pipe Classification Downstream of 1-SI-176 and 2-SI-176 from B-14 to B-12 Establishing ISI Class Break at Downstream Side of Valve 12/5/2007 2007-0362-00 Update of ESW Pump Suction Elevation NPSHa and Water Temperature Values in UFSAR Table 6.1-1 10/30/2007 2007-0362-00 Update ESW Pump Suction Elevation NPSHa and Water Temperature Values Listed in UFSAR Table 6.1-1
- MODIFICATIONS
- Number Description or Title Date or Revision
- EC 47412 Degraded Voltage Back-Fit Order Modification
- EC 475 SPV Unit 1 Reactor Coolant Pump UF Breaker Trip Elimination
- EC 48650 Remove portions of the Pipe Whip Restraints located around the Pressurizer PORV manifold piping to provide access for the installation of the PORV inverted Loop Seals per
- EC-0000047618 and Abandon In Place the remaining Pipe Whip Restraint Members
- EC 46990 U2 Refueling Water Storage Tank 8" vent pipe modification 0
- EC 47058 Install Loop Seals Between the Pressurizer PORVs and the Pressurizer PORV Block Valves
- PROCEDURES
- Number Description or Title Date or Revision
- PMP-5040-MOD-
- 010 Field Change Notices 5 PMP-5040-MOD-
- 007 Engineering Modifications 7
- 7PROCEDURES
- Number Description or Title Date or Revision
- 2-OHP-4021-054-
- 001 Operation of Condensate System 19 1-IHP-4030-182-
- 003 Reactor Coolant Pump (4 KV) Bus 1B Channel 1 Under-frequency Relay Channel Calibration
- 1-OHP-4023-ECA-0 Loss of All AC Power 24 PMP-2291-PLN-
- 001 Work Control Activity Planning Process 31 12-MHP-5021-032-041 Emergency Diesel Engine Bendix Fuel Injection Pump Removal and Installation
- OTHER DOCUMENTS
- Number Description or Title Date or Revision
- Unit 2 Degraded Voltage Back-Fit Order Post Modification Test 10/14/2007 WO 55288414-
- Unit 2 Degraded Voltage Back-Fit Order Modification Bench Test of Relays 9/17/2007 WO 55288414-
- 2-62-T21AB, Implement
- FCN-47412-007 for Train 'B' 10/3/2007 WO 55288414-
- 2-62-T21CD, Implement
- FCN-47412-007 for Train 'A' 10/7/2007
- FCN-47412-007 Dropping Resistor as Shown on
- OP-2-98050 Does Not Provide the Correct Operating Voltage for the
- NTS 812 Relay 10/2/2007
- Replace four Unit 2 AB EDG Fuel Injection Pumps 8/31/2007 WO 55230061-
- 2-PS-CGC14A-PS 1/2Replace Power Supply 9/27/2007 WO 55230061-
- 2-PS-CGC14A, Burn in Bench Check Power Supply 5/1/2007 WO 55230061-
- 2-PS-CGC14A-PS1/2, Perform "As Left" 10/12/2007
- FCN-47412-008
- FCN-47412-007 Could Not be Installed as Written 10/3/2007 NTS Manual 812-01 NTS Series 812 Timing Relays 2
- VTD-ASEA-0031 ABB Power Distribution Instructions for Single Phase Voltage Relays
- EC-0000048573 Page 14 of 31 Operating Voltage Agastat 9412 0 2-E-N-ELCP-250-007 Att.
- AB 250 VDC Battery 2AB System Analysis 2 2-E-N-ELCP-Path Voltage Drop Summary 01/19/2000
- 8OTHER DOCUMENTS
- Number Description or Title Date or Revision
- 250-006 Att. B Page B 20 of 78 2-E-N-ELCP-250-007 Att. B
- Path Voltage Drop Summary
- 01/20/2000
- ES-ESFTRT-0001-QCN ESF Time Response Basis Specification
- 3/28/2008 WO 55292116-
- CTS Heat Exchanger 1-HE-18W Shell Side Visual Inspection (including video) 4/4/2008
- WO 55292116 Open Shell Side of HTX for Inspection 4/4/2008
- 9
LIST OF ACRONYMS
- USED [[]]
VCT Volume Control Tank