IR 05000397/2007007
| ML072600321 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/14/2007 |
| From: | William Jones Division of Reactor Safety IV |
| To: | Parrish J Energy Northwest |
| References | |
| IR-06-011, IR-07-007 | |
| Download: ML072600321 (7) | |
Text
September 14, 2007
SUBJECT:
COLUMBIA GENERATING STATION - NRC COMPONENT DESIGN BASIS INSPECTION REPORT 05000397/2007007
Dear Mr. Parrish:
On August 2, 2007, the U.S. Nuclear Regulatory Commission completed a team inspection at your Columbia Generating Station. The enclosed report documents the assessments and conclusions, which were discussed on August 2, 2007, with you and other members of your staff during an exit meeting.
This inspection was an examination of activities conducted under your license as they relate to safety and compliance with the Commissions 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 2.790 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 component of NRC's document 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/
William B. Jones, Chief
Engineering Branch 1
Division of Reactor Safety
Docket: 50-397 License: NPF-21 UNITED STATES NUCLEAR REGULATORY COMMISSION R E GI ON I V 611 RYAN PLAZA DRIV E, SUITE 400 ARLINGTON, TEXAS 76011-4005
Energy Northwest
- 2 -
Enclosure:
NRC Inspection Report 05000397/2007006 w/Attachment: Supplemental Information
REGION IV==
Docket:
05000397 License:
NPF-21 Report:
05000397/2007007 Licensee:
Energy Northwest Facility:
Columbia Generating Station Location:
Richland, Washington Dates:
July 9 through August 2, 2007 Team Leader:
W. Sifre, Senior Reactor Inspector, Engineering Branch 1 Inspectors:
R. Azua, Reactor Inspector, Engineering Branch 1 B. Henderson, Reactor Inspector, Engineering Branch 1 G. Apger, Operations Engineer, Operations Branch Contractors:
C. Baron, Mechanical Contractor P. Wagner, Electrical Contractor Approved By:
William B. Jones, Chief Engineering Branch 1 Division of Reactor Safety
- 2 -
Enclosure
SUMMARY OF FINDINGS
IR 05000397/2007007; 05000323/2006011; 07/09/2007 - 08/03/2007; Columbia Generating
Station: NRC Inspection Procedure 71111.21, Component Design Basis Inspection.
The report covers an announced inspection by a team of four regional inspectors and two contractors. No violations were identified. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
NRC-Identified and Self-Revealing Findings
No findings of significance were identified.
Licensee-Identified Violations
No findings of significance were identified.
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events/Mitigating Systems/Barrier Integrity
REACTOR SAFETY
Inspection of component design bases verifies the initial design and subsequent modifications and provides monitoring of the capability of the selected components and operator actions to perform their design bases functions. As plants age, their design bases may be difficult to determine and an important design feature may be altered or disabled during a modification. The plant risk assessment model assumes the capability of safety systems and components to perform their intended safety function successfully.
This inspectable area verifies aspects of the Initiating Events, Mitigating Systems and Barrier Integrity cornerstones for which there are no indicators to measure performance.
1R21 Component Design Bases Inspection
The team selected risk-significant components and operator actions for review using information contained in the licensees probabilistic risk assessment. In general, this included components and operator actions that had a risk achievement worth factor greater than two or Birnbaum value greater than 1E-6.
a. Inspection Scope
To verify that the selected components would function as required, the team reviewed design basis assumptions, calculations, and procedures. In some instances, the team performed independent calculations to verify the appropriateness of the licensee engineers' analysis methods. The team also verified that the condition of the components was consistent with the design bases and that the tested capabilities met the required criteria.
The team reviewed maintenance work records, corrective action documents, and industry operating experience information to verify that licensee personnel considered degraded conditions and their impact on the components. For the review of operator actions, the team observed operators during simulator scenarios associated with the selected components simulated actions in the plant.
The team performed a margin assessment and detailed review of the selected risk-significant components to verify that the design bases have been correctly implemented and maintained. This design margin assessment considered original design issues, margin reductions because of modification, or margin reductions identified as a result of material condition issues. Equipment reliability issues were also considered in the selection of components for detailed review.
These included items, such as, failed performance test results; significant corrective actions; repeated maintenance; 10 CFR 50.65(a)1 status; operable, but degraded, conditions; NRC resident inspector input of problem equipment; system health reports; industry operating experience; and licensee problem equipment lists. Consideration was also given to the uniqueness and complexity of the design, operating experience, and the available defense in depth margins.
The inspection procedure requires a review of 15-20 risk-significant and low design margin components, 3-5 relatively high-risk operator actions, and 4-6 operating experience issues. The sample selection for this inspection was 17 components, 7 operator actions, and 4 operating experience items.
The components selected for review were:
- Residual heat removal pump 2B
- Reactor core isolation cooling pump P1
- Service water valve 12A
- Reactor core isolation cooling valves V45 and V22
- Switchgear ventilation 53A and 53B
- Control air compressors
- Containment instrument air
- Air operated valve TMU-LCV-1A
- Service water motor operated valve 12A
- Transformer 7-73
- Battery chargers
The selected operator actions were:
- Initiation of suppression pool cooling
- Initiation of the automatic depressurization system
- Control of reactor feedwater
- Control reactor core isolation cooling
- Control of low pressure injection
- Power conversion system recovery
- Vent containment utilization
The operating experience issues were:
- NRC Bulletin 88-04, Potential Safety -Related Pump Loss
- NRC Information Notice 2006-22, New Ultra-Low Sulfur Diesel Fuel Oil Could Adversely Impact Diesel Engine Performance
- NRC Information Notice1983-08, DC System Voltage Problems
- Periodic verification of design-basis capability of safety-related motor-operated valves
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA6 Meetings, Including Exit
On August 2, 2007, the team presented the inspection results to, Mr. D. Atkinson, Vice President Nuclear Generation and other members of the Columbia Generating Stations staff who acknowledged the findings. The inspectors confirmed that proprietary information was provided and examined during this inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
SUPPLEMENTAL IFORMATION
KEY POINTS OF CONTACT
Licensee
- D. Atkinson, Vice President Nuclear Generation and Chief Nuclear Officer
- B. Boyum, Assistant Engineering Manager
- J. Brower, Supervisor, Design Engineering
- D. Brown, Manager, Operations Support
- D. Coleman, Manager, Regulatory Programs
- J. Dittmer, Supervisor, Design Engineering
- J. Frisco, Manager, Engineering
- S. Gambhir, Vice President Technical Services
- B. LaFramboise, Manager, Design Engineering
- C. McDonald, Acting Training Engineer
- T. Morace, Project Manager, Design Engineering
- S. Sawyer, Supervisor, Quality Assurance
NRC Personnel
- Z. Dunham, Senior Resident Inspector
- R. Cohen, Resident Inspector
LIST OF DOCCUMENTS REVIEWED
Calculations
Number
Title
Revision/Date
CMR 5696
Revisions to Calc. 2.12.58
7/02/07
E/I-02-91-03
Standby Diesel Generator (DG-2) Load Calculation
E/I-02-92-01
Fuse Coordination Study for DC Distribution Systems
E/I-02-92-02
Calculation for Voltage & Torque for DC MOVs
E/I-02-92-17
Overcurrent Coordination for Medium Voltage Components
E/I-02-94-02
Calculation for DC Voltage Drop
E/I-02-94-1352
Setting Range Determination for Time Delay Relays
E/I-02-95-01
Overcurrent Settings and Coordination for 480V System
ME-02-02-26
DC MOV Thrust & Set-point Calculation
ME-02-93-28
Operator Torque Ratings for Butterfly Valves
OER81007E-1D Overvoltage Rating of Class 1E DC Devices
Feb. 1990
RTS 90-05-175
Review of OER81007E-1D Open Items
9/ 7/1990
2.05.01
Battery Sizing, Voltage Drop, and Charger Studies
2.12.18
Primary Undervoltage Relays for Buses SM-4, -7 & -8
2.12.58
Secondary Undervoltage Relays for Buses SM-4, -7 & -8
ME-02-03-10
Main Steam Isolation Valve Leakage
Number
Title
Revision/Date
CE-02-95-14
Service Water Pump SW-P-1B Dynamic Absorber
QID-213034
Qualification of Service Water Pump SW-P-1B Motor and
Dynamic Absorber
5.20.20
Pressure Drop Calculation - RCIC System
5.44.14
NPSH for ECCS Pumps with Suction Line Break
5.46.05
Maximum CIA System Pressure
216-92-018
Weaklink Analysis for Valve No. RCIC-V-45
216-92-026
Weaklink Analysis for Valve No. RCIC-V-22
216-92-040
Weaklink Analysis for Valve No. SW-V-12A,B
C106-92-03.04
SSW System MOV Design Basis Review
C106-92-03.05
RCIC System MOV Design Basis Review
E/I-02-91-03
Determine the Steady State Continuous Output for Each
Standby Diesel Generator
E/I-02-93-1272
Setting Range Determination for Instrument Loops RCIC-LS-
15A and RCIC-LS-15B
ME-02-01-30
Determination of RCIC Availability without Standby Service
Water
ME-02-02-25
MOV Thrust and Setpoint Calculation
ME-02-02-26
DC Gate and Globe Valves - MOV Thrust and Setpoint
Calculation
ME-02-04-09
Pressure Drop Verification for RCIC System
ME-02-83-21
Spray Pond Water Level Range
ME-02-89-21
Station Blackout (SBO) Coping Evaluation
ME-02-92-41
Ultimate Heat Sink Analysis
ME-02-92-43
Room Temperature Calculation for DG Building, Reactor
Building, Radwaste Building, and Service Water Pumphouse
under Design Basis and Accident Conditions
ME-02-92-44
Diesel Starting Air System Capabilities to Meet the # of Starts
Requirements
ME-02-92-234
On Site Diesel Fuel Storage for Emergency Diesel
Generators DG-1, DG-2, and DG-3
NE-02-03-06
EOP/SAG Calculations
NE-02-87-20
Oil Tank Capacity vs. Level
CMR for Calc 5-17-19 RHR Pressure Drop
CMR-1352
5.17.19 Effect of As-Built Strainer Head Losses and the
Increase of Suppression Pool Temperature on RHR PERA
200-2096-01
CMR-9500497
5.17.19 Voiding of BDC 86-0323-OB
CMR-3084
5.17.19 Rev 3 - Correct Calc Discrepancies Noted in CR 2-
04-01600
Condition Reports
0-05-00069
2-04-04235
2-05-01844
2-05-07748
2-06-07549
2-07-05799
2-04-01284
2-04-04236
2-05-01882
2-05-08784
2-07-03280
2-07-06405
2-04-01494
2-04-04309
2-05-04684
2-06-02034
2-07-05256
2-07-06908
2-04-04117
2-04-05186
2-05-06080
2-06-05849
2-07-05323
2-07-06953
2-04-04180
2-04-01863
2-04-03027
2-04-03107
2-04-03713
2-04-03750
2-05-03035
2-05-07154
2-06-00489
2-06-00648
2-06-00719
2-06-00818
2-06-05755
2-06-05849
2-06-07092
2-06-07896
2-07-00963
2-07-01014
2-07-01101
2-07-01237
2-07-01622
2-07-02156
2-07-04508
2-07-04977
2-07-05077
2-07-05182
2-07-05187
2-07-05337
2-07-06251
2-07-06385
2-07-07418
2-07-07418
2-07-07463
2-07-07518
2-07-04222
2-07-05461
2-07-05461
2-07-06426
2-07-01014
Drawings
Number
Title
Revision/Date
E502-1
Main One Line Diagram
E502-2
Main One Line Diagram
E503-1
MCC General Notes, MCC & Starter Index
E503-6
Auxiliary One Line Diagram
E503-7
Auxiliary One Line Diagram
E503-8
Auxiliary One Line Diagram
E503-9
Auxiliary One Line Diagram
E503-11
Auxiliary One Line Diagram
E503-12
Auxiliary One Line Diagram
E504
Vital One Line Diagram
E505-1
DC One Line Diagram
E505-2
DC One Line Diagram
E514-7
4160V SWGR Relay Settings SM-7
E514-19
Diesel Generator 1 Relay Settings
E514-23
DC System Relay Settings List
E515-3
480V SWGR Breaker Settings
E528-22
MCC Equipment Summary
E528-45
MCC Equipment Summary
EWD-6E-008
MOV RCIC-V-45 Wiring Diagram
EWD-6E-008A
MOV RCIC-V-45 Wiring Diagram
EWD-6E-035
MOV RCIC-V-22 Wiring Diagram
EWD-6E-035A
MOV RCIC-V-22 Wiring Diagram
EWD-46E-80A
SWGR SM-7 FDR BRKR E-CB-7/1 Wiring Diagram
EWD-46E-106A
SWGR SM-7 Undervoltage Relay Wiring Diagram
EWD-46E-107A
SWGR SM-8 Undervoltage Relay Wiring Diagram
EWD-46E-327
SWGR E-SM-4 Undervoltage Relay Wiring Diagram
EWD-47E-042
Diesel Generator 1 Engine Start/Stop Controls
EWD-47E-042A
Diesel Generator 1 Engine Start/Stop Controls
EWD-47E-048
Diesel Generator 1 Protection Circuits Schematic
EWD-50E-006A
DC Distribution Panel E-DP-S1/1D Circuit Details
EWD-50E-35A
DC Distribution Panel E-DP-S1/1F Circuit Details
EWD-58E-002
Standby Service Water Pump SW-P-1A Breaker Details
EWD-58E-002B
Standby Service Water Pump SW-P-1A Wiring Diagram
EWD-58E-020
Standby Service Water Valve SW-V-1A Details
46E080
SWGR SM-7 FDR BRK E-CB-7/1 Wiring Diagram
Number
Title
Revision/Date
46E106
E-SM-7 Critical Bus 7 Undervoltage Schematic Diagram
46E107
E-SM-8 Critical Bus 8 Undervoltage Schematic Diagram
46E159
480V SWGR SL-73 Protection Schematic Diagram
46E178
Ground Fault Indicating PNL SWGR SL-73 Diagram
90838-013
Wiring Diagram 20/25E, MFV, S-CTL, AC/WC, LUB/KT
M828
HVAC - Standby Service Water Pump Houses Plans and
Sections
M551
HVAC - Circ. Water, Make-Up Water and Service Water
Pump Houses and Diesel Generator Bldg
M501
Flow Diagram Legend, Symbols and Abbreviations
M524-1
Flow Diagram - Standby Service Water System
109
M510-1
Flow Diagram Control and Service Air System
M510-2
Flow Diagram Control and Service Air System
M510-2A
Flow Diagram Control and Service Air Systems CAS Tables
and Details
M510-3
Flow Diagram Control, Service and Breathing Air Systems
M510-4
Flow Diagram Control and Service Air Systems
M512-1
Flow Diagram - Diesel Oil and Miscellaneous Systems
M512-2
Flow Diagram - Diesel Oil and Miscellaneous Systems
M512-3
Flow Diagram - Diesel Oil and Miscellaneous Systems
M512-4
Flow Diagram - Diesel Oil and Miscellaneous Systems
M519
Flow Diagram - Rector Core Isolation Cooling System
M780
Composite Piping - Standby SW Pumphouse No. 1B
S513
S516
Standby SW Pumphouse
M556
Flow Diagram, Containment Instrument Air System
Procedures
Number
Title
Revision/Date
ABN-WIND
ECP - Tornado/High Winds
Weekly Battery Testing
Quarterly Battery Testing 125 VDC E-B1-1
ESP-RLY277172-X301
4.16KV Emergency Bus Primary Undervoltage
Relays
ESP-DIV1TRSTDR-B301
Division 1 TR-S Loss of Voltage Time Delay Relays
EnerSys (Factory) Discharge Test - Group 1 (B1-1)
2/28/06
EnerSys (Factory) Discharge Test - Group 6 (B1-2)
3/2/06
EnerSys (Factory) Discharge Test - Group 2 (B2-1)
2/28/06
EnerSys (Factory) Discharge Test - Spares
3/3/06
Shift and Daily Instrumentation Checks
PPM 5.6.1
Station Blackout (SBO)
PPM 10.2.53
Seismic Requirements for Scaffolding, Ladders,
Man-Lifts, Tool Gang Boxes, Hoists, Metal Storage
Cabinets, and Temporary Shielding Racks
Number
Title
Revision/Date
PPM 1.4.1
Plant Modifications
PPM 1.3.9
PPM 10.2.60
Installation of Fixed Ladders - Columbia Generating
Station
PPM 2.8.1A
Planned Control Air and Service Air Outage
OSP-MSIV/IST-R701
MSIV Accumulator Check Valve Operability
PPM ABN-CAS
Control Air System Failure
PPM ABN-ASH
Ash Fall
PPM 1.5.13
Preventive Maintenance Optimization Living
Program
PPM 10.25.187
Motor Control Center Starter (Bucket) Maintenance
Shift and Daily Instrument Checks (Modes 1, 2, 3)
TSP-RHRB/ RHRC - 501
RHRB/RHRC Logic System Functional Test
PPM 10.24.125
PM CAL/TEST - Magnetrol Electronic Transmitter
PPM 18.1.4
HPCS-P-1 Preservice Test
CSP-DO-C101
Diesel Generator New Fuel Test
ICP-CIA-X101
Plant Systems
RCIC Suction Transfer on CST Low Level CFT/CC
OSP-HPCS/IST-Q701
HPCS System Operability Test
RCIC Fill, Flow Controllers, and Valve Lineup
Verification
OSP-RCIC/IST-Q70
RCIC System Operability Test
OSP-RCIC/IST-Q702
RCIC Valve Operability Test
OSP-RCIC/IST-Q703
RCIC Valve Operability - Shutdown
SW Spray Pond Average Sediment Depth
Measurement
OSP-SW/IST-Q703
HPCS Service Water Operability Test
SOP-RCIC-DRAIN
RCIC Drain
SOP-RCIC-INJECTION
SOP-RCIC-FILL
RCIC Fill and Vent
SOP-RCIC-START
RCIC Start in Test Return Mode
SOP-RCIC-STBY
Placing RCIC in Standby Status
Engineering Changes/Modifications
Number
Title
Revision/Date
394
RCIC Waterhammer Prevention System Upgrades
4/9/01
5557
Assessment of Impact of 10CFR21 Communication SC06-
on Design Margin of Suppression Pool Temperature
Analysis
4/30/07
22
Evaluate Impact of MPDC 4747, HPCS Motor
Replacement on Calculation E/I-02-91-03
2/21/07
6008161
Certificate of Conformance (Exide Batteries)
3/9/06
Work Orders
01116054
01116055
01119256
01129207
01131265
01137297
01131438
01077291
01104378
01095497
01107535
01122002-01
Miscellaneous Documents
Number
Title
Revision/Date
01723-005
Design Specification for Station Blackout (SBO)
2-07-07463
CDBI Self Assessment
AR 8232
RCIC-MO-22, Evaluate Margin Restoration
1/12/05
DBD Section 308
HPCS Design Basis Document
DBD Section 309
Standby SW Design Basis Document
DBD Section 310
Standby Power Systems Design Basis Document
DBD Section 315
RCIC Design Basis Document
NRC Letter - Potential Safety Related Pump Loss
7/8/88
Health Report
RCIC System Health Report
1st Qtr 2007
Health Report
MOV Program Health Report
4th Qtr 2006
RHR, HPCS, LPCS Pumps Minimum Flow Evaluation
1/10/89
PER 205-0417
Replace HPCS-P-2
6/15/05
PER 206-0042
HPCS-P-2 May be Degraded based on SW-P-1A/1B
Pump Failure
2/2/06
PER 206-0109
Identified Non-conformance with Analyses for Suppression
Pool Water Temperature during LOCA
3/1/06
PER 206-0571
Ultra Low Sulfur Diesel Fuel
11/20/06
PER 207-0081
Ultra Low Sulfur Diesel Fuel
2/12/07
TM-1250
Volcano Ash Study
11/29/06
5059-06-003
CFR50.59 Evaluation for EC 4934, replacement of DEH
Turbine Trip System with digital PLC
RHR System Health Report
Mar 2007
Examination at NWS Technologies of Six Valves Removed
From Service at R15
June 2002
2-16
Mechanisms Resulting in Leakage from Main Steam
Safety Valves
Review of Certified Material Test Reports for Material
Effect on Disc and Nozzle Reliability
August 2002
E/I-02-91-1059
Setpoint Range and Allowable Value Determination for
Instrument Loop RHR-FIS-10A (RHR Minimum Flow)
Ingersoll Rand ECCS Pumps
GO-2-88-208
NRC Letter Subject: Potential Safety Related Pump Loss
SD000128
System Description - Main Steam System
SD000156
Containment Instrument Air
SD000201
System Description - Control Room, Cable Room and
Critical Switchgear Rooms - HVAC (CR-HVAC)
SD000205
Main Steam System
DBD Section 307
Main Steam System
DBD Section 351
Radwaste Building Mixed Air System
Number
Title
Revision/Date
DBD Section 305
Compressed Air Systems
TER 98-0103-0
Replace 480 Volt Motor WMA-FN-53A With Similar Sized
Motor
11/04/98
CER C92-0196
Inboard Main Steam Isolation Valve (MSIV) Accumulator
Check Valves 2-CIA-V-24A, B, C and D
CER C93-0690
Inboard Main Steam Isolation Valve (MSIV) Accumulator
Check Valves 2-CIA-V-24A, B, C and D
PMR 90-0026-0
Removal of CIA Compressors
09/25/91
PER 205-0499
RPS-DISC-8A2C Opened, De-energizing RPS-SYS-B,
Resulting in Half Scram
07/27/05
Lubrication Clarification for GE CR105X Contacts
BDC 89-0266-0C
Replace the Three CAS Reciprocating Compressors with
Three Sullair Rotary Screw Compressors
10/11/1990
Plant Design Changes for Extended Station Blackout
G02-91-091
Letter to NRC - Additional Information on SBO
5/7/1991
G02-94-002
Letter to NRC - Updated Information on SBO
1/6/1994
GI2-9-180
Letter to NRC - SSE SBO Analysis
6/26/1992
National Electric Code
2002
PDC 3006
10CFR50.59 Evaluation of Battery Charger Power
3/29/05
RFQ0009326
EnerSys, Inc. Letter RE: Battery Material Changes
11/22/05