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| Page Two 10 CFR PART 21 REPORT h CRITICAL POWER RATIO (CPR) CALCULATION The cladding is one of the first barriers necessary to'rovide the capability to prevent or mitigate the consequences of accidents. Thus, the reactor fuel and its supporting analysis meet the definition of a basic component as defined in the regulations. | | Page Two 10 CFR PART 21 REPORT h CRITICAL POWER RATIO (CPR) CALCULATION The cladding is one of the first barriers necessary to'rovide the capability to prevent or mitigate the consequences of accidents. Thus, the reactor fuel and its supporting analysis meet the definition of a basic component as defined in the regulations. |
| Re uirement 2 Nature of the defect or failure to comply and the Substantial Safety Hazard (SSH) which is created or could be created by such defect or failure to comply. | | Re uirement 2 Nature of the defect or failure to comply and the Substantial Safety Hazard (SSH) which is created or could be created by such defect or failure to comply. |
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| This situation is highlighted by the fact that the FWCF transient actually occurred at WNP-2 during cycle 7 on November 19, 1991. Because of the design margin, low fuel burnup, and the fact that the transient occurred from 100 percent power the minimum CPR was well above the SLNCPR as shown in Figure 2. The calculated minimum CPR during the transient was 1.35 compared to the SLNCPR of 1.07. | | This situation is highlighted by the fact that the FWCF transient actually occurred at WNP-2 during cycle 7 on November 19, 1991. Because of the design margin, low fuel burnup, and the fact that the transient occurred from 100 percent power the minimum CPR was well above the SLNCPR as shown in Figure 2. The calculated minimum CPR during the transient was 1.35 compared to the SLNCPR of 1.07. |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML17292B5331999-01-15015 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 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 ML20198E0631998-01-0707 January 1998 Part 21 Rept Re Shipment by Dubose National Energy Svcs,Inc, of 40 Pieces of 4 inch,90 Degree Elbows Which Did Not Meet ASME Section II SA-234 Requirements ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML17292A2141996-05-0808 May 1996 Part 21 Rept Re Capscrews Supplied to Wppss by Now Defunct Cardinal Industrial Products,Lp (CIP) Having Nonconforming Hardness.Failed Lots & Any Remaining Product Found to Have Been Heat Treated by CIP Scrapped & Removed from Premises ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML17291A2571994-07-22022 July 1994 Part 21 Rept Re Westinghouse Containment Penetration Modules Scotchcast Strain Relief & Varglas Insulated Conductors. Replaced Six of 12 RPIS Scotchcast/Varglas Modules & Three Scotchcast/Okonite Modules During Refueling Outage (R-9) ML17291A2351994-07-15015 July 1994 Deficiency Rept Re Material Defects in Facility Containment Penetration Modules.Initially Reported on 940715.Modules Were Replaced ML17290B2001994-05-26026 May 1994 Part 21 Rept Re Automatic Switch Co Replacement Solenoid Pilot Valve Diaphragms Supplied by GE Nuclear Energy.Unusual Combination of Scram Soleniod Pilot Valve Pressure & Exhaust Diaphragm Degradation Caused Failure of Rod to Scram ML20044G5011993-05-26026 May 1993 Part 21 Rept Re Buffer Amplifier Modules Mfg by Bailey Controls Co Containing Suspect Negative Ref Power Supply Having Safety Implications.Caused by Design Error in Circuitry.Modules Would Not Result in Miscalibration ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126D7211992-12-16016 December 1992 Potential Part 21 Rept Re Actual Performance of Rosemount Supplied Bailey Bq Differential Pressure Transmitters Differing from Rosemount Original Spec.Bailey Controls Encl.Evaluation Not Yet Performed ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML17289A8241992-08-14014 August 1992 Part 21 Rept Re Undersized Yoke Clamps on Three HPCS motor- Operated Valves Supplied by Anchor/Darling Valve Co.Nde Will Be Performed on All Clamps to Determine If Condition Affects Valve Operability.Clamps to Be Replaced by 921031 ML17289A8061992-08-14014 August 1992 Part 21 Rept Re Undersized Yoke Clamps in Three Anchor Darling HPCS motor-operated Valves.Clamps Located on Return Lines to Condensate Storage Tanks & Suppression Pool.Clamps Will Be Replaced by Util by 921031 ML17289A7991992-08-13013 August 1992 Part 21 Rept Re Limitorque Failure to Use Grade 5 Housing Cap to motor-operator Housing,Per Generic Ltr 89-10. Initially Reported on 920730.Seven GL 89-10 Category Valves Could Have Failed Due to Condition ML17289A7721992-08-0606 August 1992 Interim Part 21 Rept Re Discrepancy in Procedure Used by Siemens Nuclear Power Corp to Analyze Feedwater Controller Failure Event w/COTRANSA2 Computer Code.Initially Reported on 920709.Analysis for Cycle 8 Revised & Incorporated ML17289A7851992-07-30030 July 1992 Part 21 Rept 23965:on 920730,determined That Limitorque motor-operators Had Upper Housing Cover Cap Screws Set at 100% of Mfg Rated Thrust Which Could Fail in Svc.Caused by Installation of Grade 1 or 2 Instead of Grade 5 or 7 Screws ML17289A7521992-07-0909 July 1992 Part 21 Rept Re Discrepancy in Procedure Used to Analyze Feedwater Controller Failure Event Using COTRANSA2 Code. Initially Reported by Siemens Nuclear Power Corp on 920617. Caused by Transient Analysis Error ML17289A8591992-07-0808 July 1992 Part 21 Rept Re Delta CPR Transient Analysis Error for Feedwater Controller Failure Event Performed by Siemens Nuclear Power Corp.Feedwater Transient Actually Occurred on 911119.Fuel Cladding Failure Not Possible ML17289A6971992-06-26026 June 1992 Amend 1 to Part 21 Rept 158 Re gear-wear Induced Failures in engine-driven Jacket Water Pump in DSRV-16-4 Standby DG Sys. Initially Reported on 911029.Grand Gulf Station Observed Wear Characteristics in as Little as 500 Operating Hours ML17286B2501991-11-14014 November 1991 Part 21 Rept Re Potential Deficiency W/Asl Dry Type Transformers.Initially Reported on 910610.Recommends Issue Be Pursued W/Abb Since Westinghouse Did Not Have Necessary Technical Info or Expertise to Identify Cause or Solution ML20079B8591991-06-10010 June 1991 Interim Deviation/Noncompliance Rept 067 Re dry-type Insulator Cracking in Transformer Supplied by Westinghouse.Initially Reported on 910513.Util Notified Vendor on 910430 That Problem Affects Class 1E Transformer ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating GO2-89-144, Part 21 Rept Re Defect in Fault Tripping Design for Class 1E safety-related 480 Volt Divs 1 & 2 Ac Power Distribution Sys for Motor Control Ctrs.Caused by Improperly Designed Volt Electrical Distribution Sys.Circuit Breakers Replaced1989-08-21021 August 1989 Part 21 Rept Re Defect in Fault Tripping Design for Class 1E safety-related 480 Volt Divs 1 & 2 Ac Power Distribution Sys for Motor Control Ctrs.Caused by Improperly Designed Volt Electrical Distribution Sys.Circuit Breakers Replaced ML17285A5001989-06-0202 June 1989 Part 21 Rept Re Defect Discovered in Valve Motor Operator of RCIC Inboard Containment Isolation Valve RCIC-V-63.Upper Housing Cover Will Be Machined to Remove Excess Matl to Provide Required Recess ML17285A4771989-05-19019 May 1989 Part 21 Rept Re Defects in Target Rock Actuator Kits (Part 300562-1).Initially Reported on 890516.Defects Noted in Cold Solder Condition,Insufficient Solder Joints & Failed Solder Joints.Defective Kits Returned to Mfg for Repair ML17285A4321989-04-26026 April 1989 Part 21 Rept Re Defect in Limitorque Valve Motor Operator Model SMB-2 W/Soft Worm Shaft Clutch Gear Assembly.Caused by Failure to Install Split Spacer of Worm Shaft Clutch Gear assembly.Safety-related Valves Manually Operated ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20212A5601986-12-17017 December 1986 Part 21 Rept Re Amplified Response Spectra.Applicable Floor & Wall Mounted safety-related Equipment Reviewed & as-built Geometry & Mass of Seismic Category I Structures Compared to Original Use in Generating Amplified Response Spectra ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215B9681986-09-26026 September 1986 Part 21 & Deficiency Rept Re Synchro-Start Type Essb Speed Switches.Initially Reported on 860822.Speed Switches Currently in Svc or Designated for Svc Will Be Tested for Relay Contact Closure & Relay Contact Condition ML20210F4741986-09-16016 September 1986 Part 21 Rept Re Possible Sticking in Closed or Partially Open Position on Dresser 3050 Diaphragm Valves.Initially Reported on 850118.Disc Caps,Including Chamfers on Outside Diameter,Will Be Modified ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20195E4881986-05-23023 May 1986 Part 21 Rept Re Potential Failure of Ite/Gould Disconnect Switch,Type 7860 Ds Series.Instructions for Verification of Proper Operation of Switches Included in Notification to Plants.New Switches Available by 860901 ML20205L0921986-03-21021 March 1986 Part 21 Rept Re Throttling Requirements & Capabilities of HPI Valves Supplied to Bellefonte,Units 1 & 2 & Washington Nuclear Project.Utils Notified & B&W Suggested Listed Options for Resolving Concern ML20141F6111986-01-0303 January 1986 Interim Part 21 Rept Re Error in Computer Program Used in Analysis of Component Supports.Nuclear Pipe Support Design Guidelines Revised to Require Conversion to Another Computer Program.Final Rept by 860307 ML20137W2611985-09-30030 September 1985 Update to Part 21 Rept Re Insp for Cracked Welds Discovered in Generator Brackets.Insp for Callaway Unit 1 Postponed Until Next Refueling Outage (Probably Apr 1986).No Cracks Discovered During Insp at Wolf Creek ML20135E1161985-09-0505 September 1985 Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl ML20116E8481985-04-23023 April 1985 Part 21 Rept Forwarding Rev 1 to Insp Procedure for Investigating Emergency Diesel Generators for Fractured Welds on Air Deflectors.Rev Will Be Forwarded to Each Facility ML20100E0651985-03-29029 March 1985 Part 21 Rept Re Series of Cracked Welds Discovered in Generators.Welds Occurred in Conical Baffle Section of Coil Guards.All Units Will Be Inspected.Affected Plants Listed ML20113D7061985-01-15015 January 1985 Final Part 21 Rept Re Defective Valve Operators.Initially Reported on 841030.Control Valve Failures Resulted from Hydraulic Fluid Contamination & Improper Maint Procedures Which Allowed Aeration of Hydraulic Fluid ML20084K0111984-05-0303 May 1984 Potential Part 21 & Deficiency Rept 84-04 Re Failure to Protect Certain Cables in Dedicated Shutdown Sys.Wppss Presently Design Control Authority.Procedures Revised GO2-83-117, Final Deficiency Rept,Condition 307 Re Target Rock Isolation Valve 82M-002 on Loop B Not Closing When Deenergized. Initially Reported on 831219.Twelve Valves Disassembled, Readjusted & Reinstalled Under Vendor Supervision1983-12-20020 December 1983 Final Deficiency Rept,Condition 307 Re Target Rock Isolation Valve 82M-002 on Loop B Not Closing When Deenergized. Initially Reported on 831219.Twelve Valves Disassembled, Readjusted & Reinstalled Under Vendor Supervision ML20083G6981983-12-20020 December 1983 Revised Final Deficiency Rept,Condition 260 Re Insufficient Flow to HXs in Standby Svc Water Loops a & B.B&R Evaluating Design Error.Also Reported Per Part 21 1999-01-15
[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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Text
h.CCELERATED DISTRIBUTION DEMONSTPA.TION SYSTEM REGULSTL INFORMATION DISTRZBUTIONOZSTEM (RIDE)
ACCFSBION NBR:9208100187 DOC.DATE: 92/08/06 NOTARIZED: NO DOCKET PACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION SORENSEN,G.C. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Part 21 rept re critical power ratio calculation. Initially reported on 920617.Feedwater Controller Failure analysis &
MCPR limits revised.
DISTRIBUTION CODE: IE19D TITLE: Part 21 Rept (50 DKT)
COPIES RECEIVED:LTR Q ENCL I SIZE:
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 0 PD5 PD 1 1 DEAN,W. 1 1 INTERNAL: AEOD/DSP/ROAB 1 1 NRR/DOEA/OGCBll 2 2 NRR/DRIS/RVIB9D 1 1 I.BM 01 1 1 RES/DSIR/EIB 1 1 RGNl 1 1 RGN2 1 1 RGN3 1 1 RGN4 1 1 RGN5 1 1 SECY VANDERMEL 1 1 EXTERNAL: INPO RECORD CTR 1 1 NRC PDR 1 1 NSIC SILVER,E 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 17
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Bocc968 ~ 3000 George Wasbtngton Way ~ Richland, 1Wasbtngton 993524968 ~ (509) 372-5000 August 6, 1992 G02-92-190 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 10 CFR PART 21 REPORT A CRITICAL POWER RATIO (CPR) CALCULATION This is' 10 CFR Part 21 report submitted in accordance with the requirements of 10 CFR 21.21. Verbal notification of this condition was made to NRC Operations on July 9, 1992. The information required by the regulations is provided below:
Re uirement 1 Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
~Res onse 1 Siemens Nuclear Power Corporation 155 108th Avenue NE, PO Box 90777 Bellevue, WA 98009-0777 Siemens Nuclear Power (SNP) provides the nuclear fuel and the supporting transient analysis for WNP-2. SNP discovered a discrepancy in the procedure used to analyze the Feedwater Controller Failure (FWCF) event with the computer code COTRANSA2. This discrepancy impacted the analysis supporting Cycles 7 and 8 and involved an error in the input to the model which represents core pressurization during the FWCF event. The transient analysis for the fuel is considered a basic component since it analyzes the capability to shutdown the reactor and maintain it in a safe shutdown condition. The safety analysis guarantees cladding integrity in response to transient conditions. It provides assurance that fuel cladding failure due to lack of cooling caused by the onset of transition boiling is limited and complies with licensing requirements.
DR 92081001B7 920806 PDR'.ADOCK 05000397 8
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Page Two 10 CFR PART 21 REPORT h CRITICAL POWER RATIO (CPR) CALCULATION The cladding is one of the first barriers necessary to'rovide the capability to prevent or mitigate the consequences of accidents. Thus, the reactor fuel and its supporting analysis meet the definition of a basic component as defined in the regulations.
Re uirement 2 Nature of the defect or failure to comply and the Substantial Safety Hazard (SSH) which is created or could be created by such defect or failure to comply.
Res onse 2 One of the definitions of a defect is a condition or circumstance involving a basic component that could contribute to the exceeding of a safety limit, as defined in the WNP-2 Technical Specifications. Technical Specification paragraph 2. 1 defines the safety limits for WNP-2.
Paragraph 2. 1.2 defines the THERMAL POWER safety limit which reads in part, "The MINIMUM CRITICAL POWER RATIO (NCPR) shall not be less than 1.07 up to 4500 NWD/NTU cycle exposure and 1. 11 for cycle exposure greater than 4500 NWD/MTU to EOC." As the h CPR is used to determine the MCPR the situation described by SNP falls within this definition of a defect.
A SSH exists if there is a loss of safety function to the extent that there is a major reduction in the degree of protection provided to public health and safety. This includes exceeding a safety limit as defined in the WNP-2 Technical Specifications. The determination of a SSH for this case is aided by the attached Figure 1. The fuel and its supporting analysis was delivered with the normal design/operating margin to allow for fuel burnup and flexible rod patterns. The plant is allowed to operate at the Operating Limit Minimum Critical Power Ratio (OLNCPR) which is established by the h CPR calculation. However, Plant operation is normally well above the OLNCPR. The severity of FWCF transients is af,ected by cycle exposure. Actual plant operation during cycle 7 was limited to a cycle exposure well below the exposure of concern. However, if Cycle 7 had operated to the licensing basis energy with the licensing basis axial exposure distribution, and if the power level was between approximately 80 and 92 percent, and if assemblies were at the OLMCPR, and if a licensing basis FWCF transient had occurred, then the error in the analysis could have allowed the CPR to drop below the Safety Limit Minimum Critical Power Ratio (SLMCPR). The Supply System believes this meets the definition of a Potential Defect that could create a SSH as defined above.
This situation is highlighted by the fact that the FWCF transient actually occurred at WNP-2 during cycle 7 on November 19, 1991. Because of the design margin, low fuel burnup, and the fact that the transient occurred from 100 percent power the minimum CPR was well above the SLNCPR as shown in Figure 2. The calculated minimum CPR during the transient was 1.35 compared to the SLNCPR of 1.07.
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.'Page Three 10 .CFR PART 21 REPORT b, CRITICAL POWER RATIO (CPR) CALCULATION Re uirement 3 The date on which the information of such defect or failure to comply was obtained.
Res onse 3 June 17, 1992 Re uirement 4 In the case of a basic component which contains a defect or fails to comply, the number and location of all such components in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulations of this part.
Res onse 4 WNP-2 does not have the information to respond to this question as it was the purchaser, not the supplier, of the basic component. However, SNP has stated that they have notified all of their affected customers.
Re uirement 5 The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.
Res onse 5 Corrective action to address this concern at WNP-2 has been completed. At the time of notification of the defect, June 17, 1992, SNP had completed their evaluation of the non-conservatism in the FWCF analysis and had established input changes to correct the modeling of core pressurization during FWCF analysis performed with the COTRANSA2 code. Supply System reviews of the non-conservatism concluded the procedural change implement-ed by SNP was acceptable for FWCF analysis performed with COTRANSA2. SNP was requested to revise the FWCF analysis for Cycle 8 and provide revised HCPR limits for incorporation into the Core Operating Limits Report (COLR). The revised limits were also incorporated into the core monitor-ing system (POWERPLEX) for use in monitoring thermal operating limits.
These actions were completed prior to plant restart in early July 1992.
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"Page Four 10 CFR PART 21 REPORT h CRITICAL POWER RATIO (CPR) CALCULATION
~Ri 66 Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.
Res onse 6 WNP-2 is the purchaser and licensee and does not have any advice to relate.
Any questions concerning this report should be referred to Mr. C.L. Fies, Compliance Engineer, (509) 377-4147.
Sincerely, G. C. gorensen, Manager Regulatory Programs (Mail Drop 280)
CLF/bk Attachments cc: JB Martin - NRC RV NS Reynolds - Winston 5 Strawn RR Assa - NRC DL Williams - BPA/399 NRC Site Inspector - 901A U. Fresk - SNP
FIGURE 1 TYPICAL CRITICA PQMER RATIQ (CPR) APPLICATION QPERATING 1,'18-1,78 CPR DESIGN/OPERATING MARGIN 1,18-1,39 QPERATING LIMIT MCPR (QLMCPR)
MARGIN FQR TRANSIENT EVENT (F4'CF)
MCPR 1,85-1,87 SAFETY LIMIT MCPR (SLMCPR)
MARGIN FQR UNCERTAINTIES 1,88 MEAN QF CPR CQRRELATIQN
FIGURE 2 CRITICAL PQMER RATIQ (CPR)
DURING FWCF EVENT NQV 19, 1991 1,'j2 PESIGNyQP ERA TING MARGIN OPERATING MINIMUM CPR ~
DURING EVENT 1,35 1,23 MARGIN FQR TRANSIENT M CPR = 8.16 FOR BOUNDING CREE M CPR = 8,87 FOR FWCF 1,87 SAFETY LIHIT HCPR (S LMCPR)
MARGIN FQR UNCERTA'INTIES 1,88 HEAN OF CPR CORRELATION