GO2-04-165, License Amendment Request - Removal of the Monthly Operating Report and the Occupational Radiation Exposure Report from Technical Specification Using the Consolidated Line Item Improvement Process
GO2-04-137, Request for Amendment to Technical Specifications for One-Time Extension of Containment Leak Rate Test Interval
GO2-04-088, Annual Report of Individual Monitoring
GO2-03-187, Letter of Intent to Participate in Probabilistic Risk Assessment Quality Pilot Application Program
GO2-03-167, Revision to Technical Specification LCO 3.0.4 and SR 3.0.4 Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process (CLIIP)
GO2-03-040, Annual Operating Report 2002
GO2-03-038, Transmittal of Columbia Generating Station Radioactive Effluent Release Report for 2002
GO2-03-029, Request for Enforcement Discretion from Technical Specification 3.8.1, A.C. Sources - Operating.
GO2-02-138, (WNP-2) Application for Amendment to License NPF-21, for Three Changes to Technical Specifications 4.2.1 & 5.6.5.b
GO2-02-135, Revised Request for Amendment on the Alternate Source Term
GO2-02-134, Energy Northwest, Docket No. 50-397, NRC Inspection Report 50-397/02-05, Response to Notice of Violation
GO2-02-121, Fitness for Duty Semiannual Performance Data Report January 1 to June 30, 2002
GO2-02-114, Application for Technical Specification Change Regarding Missed Surveillances Using the Consolidated Line Item Improvement Process
GO2-02-113, 2002 Exercise Scenario Submittal
GO2-02-111, Amendment Request to Revise Minimum Emergency Diesel Generator Output Voltage Specified in Technical Specification Limiting Condition for Operation 3.8.1
GO2-02-066, Request for Amendment Re Technical Specification 5.5.10, Technical Specification (TS) Bases Control Program
GO2-02-054, 14-Day Follow-up Report Regarding a Violation of Operating License Condition 2.E
GO2-02-033, Fitness for Duty Semiannual Performance Data Report July 1 to December 31, 2001
GO2-02-016, Operating License NPF-21 Reply to Final Significance Determination for a Yellow Finding and Notice of Violation (NRC IR 05000397/2001-008)
GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With
GO2-97-089, Comment Supporting Proposed Rule 10CFR73 Re Changes to Power Plant Security Requirements
GO2-99-162, Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d)
GO2-99-133, Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112
GO2-99-074, Responds to NRC Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security
GO2-99-099, Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date
GO2-98-025, Informs That DW Coleman Now Acting as Manager,Regulatory Affairs for Facility.Std Distribution for Documents Sent to Util Should Be Modified
GO2-98-038, WNP-2 Annual Operating Rept for 1997
GO2-97-223, Provides Info in Compliance w/10CFR140.21,which Requires Annual Filing of Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each Licensed Reactor
GO2-97-162, Forwards Fitness for Duty Semiannual Performance Data Rept for Jan-June 1997
GO2-97-158, LER 97-S01-00:on 970718,failure to Take Compensatory Measure for Inoperative Microwave Security Zone Occurred. Caused by Personnel Error.Training Will Be Conducted W/ Appropriate Members of Security Force
GO2-97-098, Responds to NRC Re Insp Rept 50-397/97-08.Util Recently Completed Annual Concerns Program Training Cycle Which Included Survey of 971 Supply Sys & Contractor Employees.Insp Rept Points Out Some Areas of Improvement
GO2-97-019, Comments on Final Draft SE of Proposed Conversion to Improved TS
05000397/LER-1996-008, :on 961205,failure to Comply with TS Action Requirement for Emergency Core Cooling Sys Actuation Instrumentation Occurred Due to Unidentified Inoperability Condition.Pmr Initiated
GO2-96-234, Submits Guarantee of Payment of Deferred Premium for $10 Million Dollars,Per 10CFR140.21
GO2-96-169, Forwards FFD Semiannual Performance Data Rept for 960101 to 0630
GO2-96-230, Responds to NRC Re Exercise Weakness in Insp Rept 50-397/96-14.Corrective Actions:Reiterated Mgt Expectations Associated W/Offsite Notification Process to Appropriate Personnel Responsible for Protective Action Recommendations
05000397/LER-1996-006, :on 960709,average Power Range Monitor Rod Block Downscale Surveillance Not Performed Prior to Entry Into Mode 1.Caused by long-standing Misinterpretation of Requirements of Tss.Procedures Revised
GO2-97-038, Forwards Fitness for Duty Semiannual Performance Data Rept for Jul-Dec 1996
GO2-96-093, Operational Ecological Monitoring Program for Nuclear Plant 2,1995 Annual Rept
GO2-96-090, WPPSS 2 1995 Annual Rept Jan-Dec 1995 of Radiological Environ Monitoring Program
GO2-97-012, Requests Withdrawal of Request for Amend to TS 6.0, Administrative Controls
GO2-96-190, Responds to Exercise Weakness in Insp Rept 50-397/96-13. Corrective Actions:Each Operating Crew Has Received Addl Training on Use of High Range Stack Monitor & Participated in Simulator Training
GO2-96-216, Provides Addl Info to Assist NRC in Evaluating Issues in Insp Rept 50-397/96-16 & NOV
GO2-97-024, Comments on Final Dser,Including Request to Increase Allowable Start Times for EDGs
GO2-97-156, Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line
GO2-97-222, Ack Receipt of 971203 Transmittal of Insp Rept 50-397/96-22. Response to Subject Insp Rept Will Be Submitted on or Before 980121,as Discussed in Telcon
GO2-97-043, Annual Operating Rept for 1996
GO2-98-154, Forwards Response to Violations Noted in Insp Rept 50-397/98-14.Corrective Actions:Individuals Involved in Emergency Plan Rev Process Counseled Re Need to Ensure Emergency Plan Meets Requirements of 10CFR50 App E
GO2-98-149, Forwards fitness-for-duty semi-annual Performance Data Rept for 980101-0630,per 10CFR26.71(d).Data Has Been Analyzed & Mgt Actions Have Been Taken to Enhance Program
GO2-99-035, Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint
GO2-98-020, Forwards Fitness for Duty Semiannual Performance Data Rept for 970701-1231
GO2-98-101, Provides Requested 30 Day Rept Re Insp of Reactor Core Shroud Welds for Indications of Stress Corrosion Cracking. Shroud Insp Requested by Has Been Completed
GO2-98-111, Ro:On 980617,flooding of RB Northeast Stairwell with Consequential Flooding of Two ECCS Pump Rooms.Caused by Inadequate Fire Protection Sys Design.Pumped Out Water from Affected Areas to Point Below Berm Areas of Pump Rooms
GO2-99-041, WNP-2 1998 Annual Operating Rept. with
GO2-98-107, Informs That DW Coleman Has Been Appointed Regulatory Affairs Manager & Records Should Be Corrected to Reflect Change
GO2-99-062, Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule
GO2-98-205, Responds to NRC Re Violations Noted in Insp Rept 50-397/98-15.Corrective Actions:Implemented ACs to Ensure That Adequate Supply of Water Is Maintained in Each Storage Tank to Provide Vol Suction Source for HPCS & RCIC Pumps
GO2-98-208, Submits Guarantee of Payment of Deferred Premium in Compliance with 10CFR140.21
GO2-99-021, Forwards WNP-2 Fitness for Duty Semiannual Performance Data Rept for Jul-Dec 1998,per 10CFR26.71(d).Data Has Been Analyzed & Mgt Actions Have Been Taken to Enhance FFD Program
GO2-99-146, Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown
GO2-99-155, Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety
GO2-99-143, Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a
GO2-99-144, Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level
GO2-98-216, Responds to NRC Re Violations Noted in Insp Rept 50-397/98-20.Corrective Actions:Implemented Interim Actions to Assure That Significant Pressure Surges Do Not Occur in Plant Fire Protection Sys
GO2-99-142, Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring
GO2-99-086, Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790
GO2-98-045, Forwards Copy of Performance Self-Assessment,WNP-2, Documenting Results of Assessment,Which Was Conducted 971006-31,of Key Functional Areas
05000397/LER-2004-006, Regarding Reactor Manual Scram During Plant Startup Due to High Water Level in the Pumped Drain Tank, and LER 04-006-00 Regarding Reactor Manual Scram During Reactor Startup Due to Improper Restoration of
05000397/LER-2004-004, Regarding Items of Reportability and Corrective Actions Taken
05000397/LER-2004-002, Reactor Core Isolation Cooling Declared Inoperable Due to Relay Failure
05000397/LER-2001-003, Regarding Inoperable High Pressure Core Spray (HPCS) System Due to Lower System Pressure
05000397/LER-2003-010, Regarding Unanticipated Inoperability of the Single Train High Pressure Core Spray System
05000397/LER-2003-009, Regarding Reactor Core Isolation Cooling Rendered Inoperable Due to a 250 Vdc Battery Cell Not Meeting TS Requirements
05000397/LER-2003-008, Reactor Core Isolation Due to Inadvertent Closure of Containment Isolation Valve During Testing
05000397/LER-2003-007, Automatic Reactor Scram Due to a Main Transformer Differential Current Relay Actuation
05000397/LER-2003-004, For Columbia Generating Station Re Condition Prohibited by Technical Specifications Limiting Condition for Operation 3.10.4
05000397/LER-2003-005, For Columbia Generating Station, Shutdown Cooling Isolation Caused by Procedure Deficiency
05000397/LER-2003-001, For Columbia Residual Heat Removal (RHR) B Train Potentially Inoperable During a Design Basis Event Due to Apparent Inability of System to Adequately Maintain Pressure as Assumed in Appendix R Analysis
05000397/LER-2003-006, Regarding Failure to Restore Emergency Diesel Generator within TS Completion Time & Subsequent Plant Shutdown
05000397/LER-2002-003, Water Leakage Paths Through Fire Rated Floor Assemblies on May 3, 2002
05000397/LER-2002-001, Re Completion of Technical Specification Required Shutdown Fo Comply with Technical Specification LCO 3.8.1 Required Actions of Condition F
GO2-02-027, Stations Clarification and Response Regarding NRC IR 05000397/2001-008 and Final Significance Determination Letter
GO2-02-003, Operating License NPF-21, Request for Amendment to Technical Specifications for Extension of Interval from 18 to 24 Months for Selected Surveillance Requirements