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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML17292B2641998-03-0404 March 1998 Performance Self Assessment,WNP-2. ML17292A3921996-06-30030 June 1996 WNP-2 Ten Mile EPZ Evacuation Time Estimate Study. ML17291B2931995-12-31031 December 1995 Adjustable-Speed Drive Retrofit for Ormond Beach Fd Fans. ML17291B1401995-07-0606 July 1995 Technical Evaluation Rept,Wppss Plant No 2,Pump & Valve Ist,Rev 0,Second Ten-Yr Interval. ML17291A9421995-06-30030 June 1995 Rev 0 to IPE of External Events WNP2. ML17291A5691994-12-0707 December 1994 Simulator Facility Certification. ML17291A4481994-10-13013 October 1994 WNP-2 Response to Request for Addl Info on Emergency Classification. ML17290A9181993-12-27027 December 1993 Justification for Revised Tornado Design Criteria,Rev 1. ML17290A6901993-10-0808 October 1993 Revised Significant Hazards Consideration Assessment for WNP-2 Power Uprate W/Elll. ML17290A6861993-09-27027 September 1993 Rev 1 to Evaluation of Sources of Radioactive Matl Found in Cooling Tower Sediments at Washington Nuclear Plant 2. ML17290A3831993-05-18018 May 1993 Rept R-R8-111 Re Flaw in Reactor Recirculation Piping ML17289B0751992-11-23023 November 1992 Rev 0 to Technical Memorandum Tm 2025, Secondary Containment/Standby Gas Treatment Design Basis. ML17289A9881992-10-0707 October 1992 Containment Atmosphere Control Sys (CAC) Summary Issues. ML17289A7251992-06-30030 June 1992 Institutional Custody Fiduciary Svcs. ML17289A7231992-06-30030 June 1992 Institutional Custody Fiduciary Svcs. ML17289A9281992-06-24024 June 1992 WNP-2 Simulator Certification NRC Form 474 Supporting Documentation. ML17289A5351992-05-11011 May 1992 App B, 8X8 Extended Burnup, of EMF-92-040, WNP-2 Cycle 8 Reload Analysis. ML17286B0211991-08-20020 August 1991 Root Cause Analysis Summary, Unsatisfactory Licensed Operator Requalification Program, Reflecting Causes of Operators Continued Inability to Respond to Severe Accident Conditions ML17286A9151991-06-30030 June 1991 Asset Summary 910630. ML17286A9141991-06-30030 June 1991 Summary of Transactions for 900630-910630. ML17285A9631989-12-27027 December 1989 Feedwater Nozzle Insp Rept for Refueling Outage RF89A Spring 1989. ML17285A8871989-08-14014 August 1989 Rev 0 to Commercial Grade Dedication Project for Wppss Contract C-30298. ML17285A6411989-07-31031 July 1989 Instrument Air Sys Review Response to Generic Ltr 88-14. W/Six Oversize Figures ML17285A1971988-12-14014 December 1988 Feedwater Nozzle Insp Rept for Refueling Outage RF88A, Spring,1988. ML20237D3121987-11-30030 November 1987 Final Feedwater Temp Reduction Summary Rept ML17279A6251987-04-30030 April 1987 Rev 2A to Wnp 1,2 10-Mile EPZ Evacuation Time Assessment Study. ML17279A1911987-04-0707 April 1987 Comparision of Electrical Design of Wye Pattern Globe Valve Actuator W/Ball Valve,Hanford 2 & River Bend Design. Five Oversize Drawings Encl ML17279A2341987-03-31031 March 1987 Washington Nuclear Plant 2 Performance Indicator Rept. ML20207N2661986-12-31031 December 1986 Assessment of Fire Protection Program Responsibilities & Administration ML20215B7271986-11-25025 November 1986 Feedwater Nozzle Insp Rept for Refueling Outage RF86A, Spring 1986 ML17278B0001986-08-22022 August 1986 Results of Insp of WPPSS-2 Cycle 1 Discharge Fuel. ML17279A6481986-05-0101 May 1986 Draft Lead Test Assembly Program,Wpps 2. ML17278A8051986-03-31031 March 1986 Safety Review of Wppss Nuclear Project 2 at Core Flow Conditions Above Rated Flow Throughout Cycle 1 & Final Feedwater Temp Reduction. ML17278A4721985-09-30030 September 1985 Crdr & Emergency Procedure Functional Task Analysis Summary Rept. ML17278A4281985-07-31031 July 1985 Washington Nuclear Plant Unit 2 Spray Pond Drift Loss Rept. ML17277B6191985-01-31031 January 1985 Rev 2 to Description of Early Warning Sys for Wppss Nuclear Plants 1 & 2. ML17277B5241984-10-0808 October 1984 Feedwater Piping Thermal Deflection Events, Final Design Engineering Rept ML17277B2451983-12-30030 December 1983 RHR Addendum to Design Verification Program. ML17277B2201983-12-11011 December 1983 Qualification of Purge & Vent Valves at WPPSS-2, Vols 1 & 2 ML20080N1941983-12-0707 December 1983 Excerpt from Qvp Overview Rept,Vol I,Book 1 of 1.Related Info Encl ML17277B2961983-11-30030 November 1983 Rept to Governor J Spellman of State of Wa & Governor V Atiyeh of State of Or. ML17277B2231983-11-0808 November 1983 Qualification of Purge & Vent Valves at WPPSS-2, Vol 4: Rev 4 to Equipment Seismic & Hydrodynamic Requalification of 24-Inch Cylinder Operated Butterfly Valves for CSP-V-3, 4,5,6 & 9 & CEP-V-3A & 4A. ML17277B2221983-11-0404 November 1983 Qualification of Purge & Vent Valves at WPPSS-2, Vol 3: Rev 2 to Equipment Seismic & Hydrodynamic Requalification of 30-Inch Cylinder Operated Butterfly Valves CSP-V-1 & 2 & CEP-V-1A & 2A. ML17277A9431983-10-0707 October 1983 Response to NRC Human Factors Engineering Preliminary Design Assessment Audit Rept of 830826. ML17277A8701983-09-30030 September 1983 Design Reverification Program, Vols 1 & 2,final Assessment Rept ML20078M2661983-09-30030 September 1983 Independent Evaluation of Plant Verification Program at WPPSS-2:Vol I Quality Verification ML20080T2071983-09-22022 September 1983 Engineering Insp & Evaluation of Quality Class Ii/Seismic Category I Pipe Supports ML17277A8541983-09-21021 September 1983 Quality Verification Program,Vol 1:Overview Rept,Jul-Sept 1983. ML17292A8091983-09-20020 September 1983 Sheet 1 to Reactor Protection Sys. ML17277A9961983-09-0909 September 1983 Hanford 2 Power Generation Control Complex (Pgcc) Floor Plate Design. 1998-03-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999 Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR 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.With1999-10-0101 October 1999 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 ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr ML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr ML17292B6641999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr ML17292B5571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for WNP-2.With 990210 Ltr ML17292B5621999-01-31031 January 1999 Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr. ML17292B5341999-01-15015 January 1999 Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error ML17292B5331999-01-15015 January 1999 Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE ML17292B4791998-12-31031 December 1998 Washington Public Power Supply Sys 1998 Annual Rept. with 981215 Ltr ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr ML17292B5741998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with 990225 Ltr ML17284A8231998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With 981207 Ltr ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7831998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for WNP-2.With 981007 Ltr ML17284A7491998-09-10010 September 1998 WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998. ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7681998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for WNP-2.With 980915 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for WNP-2.W/980810 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6751998-06-30030 June 1998 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 ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17284A6491998-05-31031 May 1998 Rev 0 to COLR 98-14, WNP-2,Cycle 14 Colr. ML17292B4031998-05-31031 May 1998 Monthly Operating Rept for May 1998 for WNP-2.W/980608 Ltr ML17292B3921998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for WNP-2.W/980513 Ltr ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3371998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for WNP-2.W/980409 Ltr ML17292B2641998-03-0404 March 1998 Performance Self Assessment,WNP-2. ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B2911998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for WNP-2.W/980313 Ltr ML17284A7971998-02-17017 February 1998 Rev 28 to Operational QA Program Description, WPPSS-QA-004.With Proposed Rev 29 ML17292B3591998-02-12012 February 1998 WNP-2 Cycle 14 Reload Design Rept. 1999-09-30
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8609200484 860903 PDR APgCg 0g0003yy I' PDR RESULTS OF THE INSPECTION OF WNP-2 CYCLE I DISCHARGED FUEL August 22, 1986 By: D.P. Chan N.C. Humphreys R.J. Ta1bert W.C. Wo1kenhauer
C e Results of the Examination The assemblies appeared to have good structural integrity. The upper tie plates were level, rod springs had ample compression space, tie rod nuts were snug, there was not apparent rod bow and all rods were properly seated in the lower tie plate. The spacers were perpendicular to the rods and properly located.
Small scratches attributed to channeling and dechanneling were observed on some peripheral fuel pins and on spacer surfaces. Several locking tab washers were bent. In general, the mechanical integrity of the fuel appears to be good.
On the seven medium enriched bundles, nodular corrosion was observed on some of the spacer grids. The nodules can be characterized as ranging from discrete nodules to relatively complete coverage. On these same bundles, the fuel pins exhibit large areas completely covered with a white-appearing layer. At the extremes of the covered regions, a region 'covered in varying degrees with white pa'rticles can be observed.
This spotted region can be found as a transition zone both above and below the completely covered region. Typically, the extreme ends of the fuel pins are free of any apparent deposit.
The apparent thickness of the deposition layer seems to correlate with the specific power being generated by the fuel. The apparent peak deposition on the fuel appears to be approximately one third up the fuel.
A key question is the composition of the observed deposition on the fuel. General Electric has characterized it as crud. They believe that if it were brushed off, some nodular corrosion would be observed.
Another reviewer has characterized the deposit itself as nodular corro-sion. It appears to Supply System engineers that at least some of the deposition is nodular corrosion rather than crud.
The one assembly of natural enrichment appear to be relatively free of any corrosion or crud.
~Sammar The inspected fuel appears to be free of significant mechanical damage.
Mechanical phenomena appear to be limited to minor scratches and distor-tion of the tie rod locking tab washers. The rod locking tab washers were probably distorted during channeling.
Nodular corrosion to a significant degree exists on some of the spacer grids; some nodular corrosion also exists on some of the fuel pins. The specific degree of nodular corrosion on the fuel cannot be further charac-terized except to say that it is apparent the integrity of the fuel is not presently at risk.
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Introduction In accordance with the WNP-2 FSAR, Section 4.2.4.3, a visual inspection of discharged fuel assemblies from WNP-2, Cycle 1, was performed.
Selection of Assemblies Eight assemblies were selected for inspection representing greater than 5 percent of the discharged fuel (see Figure 1 attached). The selected assemblies included seven medium enriched assemblies and one natural assembly. They were selected to be representative of the total dis-charged fuel batch. Four assemblies, LJT 270,- LJT 187, LJT 255, and LJT 216 were located in symmetric locations in the core and, in addition, are the high burnup assemblies discharged at the end of Cycle 1. They are all medium enriched assemblies. Three assemblies, LJT 295, LJT 248, and LJT 218, when combined with LJT 216 mentioned above, constitute a radial line from the high burnup location towards the core center.
These three assemblies are also medium enriched. LJT 144 is a natural enriched bundle located on the core periphery along the same radial line defined by LJT 295, LJT 248, etc. Given the excellent core power symmetry that WNP-2 observed during Cycle 1, the selected pattern of assemblies to be inspected represents the spatial and exposure effects of the total discharge batch from Cycle 1.
Ins ection Techni ue The poolside visual examination was performed by means of an underwater camera system with the results of the fuel inspection being recorded on video tape. In general, two sides of each fuel assembly selected for inspection were viewed. The sides viewed were orientated based on the location indicator on the assembly bale handle. The inspection procedure involved moving the fuel assembly in a vertical direction past the fixed camera. This was accomplished by placing the fuel assembly in the fuel preparation machine and utilizing the fuel preparation machine as an elevator. In a typical inspection, a view was first taken of the upper bale and then one side viewed top to bottom. The camera was then moved to a location 90 degrees to the initial locat'ion and a second side viewed bottom to top as the fuel preparation machine was driven down.
Ins ection Criteria Visual inspection of the selected assemblies was performed to determine the extent of the following phenomena:
~ Proper rod seating in the lower tie plate.
~ Rod bow and spacing.
~ Spacer location and perpendicularity.
~ Relative rod growth.
~ Condition of tie rod hex nuts and other structural components.
~ Nodular corrosion and crud formation.
~ Rod fretting.
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