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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML17284A6751998-06-30030 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 ML17292A7921997-04-0909 April 1997 Ro:On 970327,reactor Scrammed.Evaluation Results,Conclusions & Corrective Actions Will Be Shared W/Nrc Prior to Plant Startup from Maint & Refueling Outage ML17291A6961995-03-16016 March 1995 Special Rept:On 950305,reactor Bldg Effluent Monitoring Sys Was Inoperable for 72 Hrs.Caused by Failure of Stack Monitor Detector.Stack Monitor Returned to Svc on 950314 1998-06-30
[Table view] Category:LER)
MONTHYEARML17284A6751998-06-30030 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 ML17292A7921997-04-0909 April 1997 Ro:On 970327,reactor Scrammed.Evaluation Results,Conclusions & Corrective Actions Will Be Shared W/Nrc Prior to Plant Startup from Maint & Refueling Outage ML17291A6961995-03-16016 March 1995 Special Rept:On 950305,reactor Bldg Effluent Monitoring Sys Was Inoperable for 72 Hrs.Caused by Failure of Stack Monitor Detector.Stack Monitor Returned to Svc on 950314 1998-06-30
[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 GO2-99-180, Monthly Operating Rept for Sept 1999 for WNP-2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With GO2-99-170, Monthly Operating Rept for Aug 1999 for WNP-2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With GO2-99-156, Monthly Operating Rept for July 1999 for WNP-2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With ML17284A8331999-07-30030 July 1999 Safety Evaluation Supporting Proposed Alternative of Direct or Remote VT-1 Visual Exam of Pump Casing Welds Will Be Capable of Detecting Any Known Degradation in Carbon Steel Welds,Therefore Provides Assurance of Pressure Integrity 05000397/LER-1999-001, :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. with1999-07-20020 July 1999
- 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
GO2-99-124, Monthly Operating Rept for June 1999 for WNP-2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With GO2-99-106, Monthly Operating Repts for May 1999 for WNP-2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With GO2-99-089, Monthly Operating Rept for Apr 1999 for WNP-2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With GO2-99-069, Monthly Operating Rept for Mar 1999 for WNP-2.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With ML17292B6061999-03-25025 March 1999 Safety Evaluation Accepting Relief Request RV02 ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr GO2-99-048, Monthly Operating Rept for Feb 1999 for WNP-2.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With ML17292B5621999-01-31031 January 1999 Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr. GO2-99-028, Monthly Operating Rept for Jan 1999 for WNP-2.With1999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for WNP-2.With ML17292B5401999-01-27027 January 1999 Safety Evaluation Supporting Amend 156 to License NPF-21 LD-99-003, 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-CE1999-01-15015 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 LD-99-002, 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 Error1999-01-15015 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 GO2-98-211, Washington Public Power Supply Sys 1998 Annual Rept. with1998-12-31031 December 1998 Washington Public Power Supply Sys 1998 Annual Rept. with GO2-99-041, WNP-2 1998 Annual Operating Rept. with1998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with GO2-99-006, Monthly Operating Rept for Dec 1998 for WNP-2.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr ML17292B5061998-12-30030 December 1998 Safety Evaluation Accepting Licensee Proposed Rev 26 to Operational Quality Assurance Program Description ML17292B4911998-12-21021 December 1998 Safety Evaluation Accepting Proposed Rev 29 to Operational Quality Assurance Program GO2-98-204, Monthly Operating Rept for Nov 1998 for WNP-2.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With GO2-98-188, Monthly Operating Rept for Oct 1998 for WNP-2.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr 05000397/LER-1998-012, :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.With1998-10-27027 October 1998
- 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
GO2-98-174, Monthly Operating Rept for Sept 1998 for WNP-2.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for WNP-2.With ML17284A7491998-09-10010 September 1998 WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998 05000397/LER-1998-013, :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.With1998-09-0303 September 1998
- 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
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 05000397/LER-1998-015, :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.With1998-09-0202 September 1998
- 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
05000397/LER-1998-014, :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.With1998-09-0202 September 1998
- 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
GO2-98-166, Monthly Operating Rept for Aug 1998 for WNP-2.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for WNP-2.With GO2-98-144, Monthly Operating Rept for July 1998 for WNP-21998-07-31031 July 1998 Monthly Operating Rept for July 1998 for WNP-2 05000397/LER-1998-006, :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 Changes1998-07-23023 July 1998
- 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
05000397/LER-1998-011, :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 Conducted1998-07-17017 July 1998
- 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
05000397/LER-1998-010, :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 Tubing1998-07-15015 July 1998
- 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
05000397/LER-1998-009, :on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in Preparation1998-07-0101 July 1998
- on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in Preparation
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 GO2-98-119, Monthly Operating Rept for June 1998 for WNP-21998-06-30030 June 1998 Monthly Operating Rept for June 1998 for WNP-2 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 Rooms1998-06-30030 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 05000397/LER-1998-007, :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 Event1998-06-24024 June 1998
- 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
05000397/LER-1998-008, :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 Lines1998-06-24024 June 1998
- 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
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 05000397/LER-1998-005, :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 Limitation1998-06-0404 June 1998
- 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
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 1999-09-30
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<CCELERATED DlgR1BU'TlON DEMONST+TlON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8909250014 DOC.DATE: 89/09/14.NOTARIZED:
NO FACIAL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION POWERS,C.M.
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION MARTIN,J.B.
Region 5, Ofc of the Director
SUBJECT:
Special rept:on 890821,post-accident sampling primary coolant radiation monitor.DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR J ENCL/SIZE'TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: DOCKET I 05000397 I R'D'RECIPIENT ID CODE/NAME PD5 LA SAMWORTH,R COPIES LTTR EN 1 1 CL RECIPIENT ID CODE/NAME PD5 PD COPIES LTTR ENCL INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB DEDRO NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RES/DSIR/EIB EXTERNAL: EG&G WILLIAMS,S LPDR NSIC MAYS,G NUDOCS FULL TXT NOZE'IO ALLRIBS" RECIPIIRIS:
ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP
" IRM/DCTS/DAB NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/PEB 10 NRRtBBB RPB 10 EG FILE 02 RGN5 LE Ol L ST LOBBY WARD NRC PDR NSIC MURPHYIG~A 8 I D D D S PIZASE HELP US'IO REEVE HASTE!CGHIMT'IHE DOI.'X3KKI'KNIBOL DESK, RXM Pl-37 (EXT.20079)K)EEiZKMQR KXK NAKE FR%DIBTRZBUZICN TOTAL NUMBER%PVOVRP%+%%8P
%M%5 ENCL~0
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.o.Box 968~3000 George Washington Way~Richland, Washington 99352 Docket No.50-397 September 14, 1989 V Mr.J.8.Hartin Regional Administrator USNRC, Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596
Dear Mr.Martin:
Subject:
NUCLEAR PLANT NO.2 LICENSE NO.NPF-21 SPECIAL REPORT: POST-ACCIDENT SAMPLING PRIMARY COOLANT RADIATION MONITOR This special report is submitted pursuant to the requirements of WNP-2 Tech-nicall Specification Table 3.3.7.5-1 (Instrument
'o.29: Post-Accident Sampling Primary Coolant Radiation Monitor), Action Statement 81.Action Statement 81 requires","with the number of operable accident monitoring instrumentation channels less than required by the minimum channels operable requirement,, either restore the inoperable channel(s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or: (a)Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and (b)In lieu of any other report required by Specification 6.9.1 prepare and submit a Special Report to the commission pursuant to Specification 6.9.2 within 14 days following the event outlining the'ction taken, the cause of.the inoperability and the plans and schedule for restoring the system to operable status."
J.B.Hartin Page 2 September 14, 1989 SPECIAL REPORT: POST-ACCIDENT SAMPLING PRIMARY COOLANT RADIATION MONITOR On August 21, 1989, during routine Post-Accident Sampling System (PASS)train-ing for Plant Chemistry Personnel, it was noted that PASS Containment Isola-tion Valves PSR-V-X77A/3 and PSR-V-X77A/4 appeared to leak when in the closed~position.Accordingly, the valves were isolated by closing PSR-V-104 (Jet Pump 20 Sample Line Isolation Valve)and the LCO was entered.On August 24, 1989 PSR-V-104 was opened and the system returned to service, within the 72-hour LCO time frame.After further review of the situation, the decision was made to manually isolate the valves to prevent back leakage of Jet Pumps 10 and 20 to the Demineralized Water System., On August 31, 1989, the valves were again isolated by closing PSR-V-104 (PSR-V-107, Jet Pump 10 Sample Line Isolation Valve, had previously been closed due to leakage from PASS Contain-ment Isolation Valves PSR-V-X77A/1 and PSR-V-X77A/2).
Because the system is inoperable, Post-Accident Sampling Primary Coolant Radiation Monitor PSR-RI-665 is unable to perform its intended function as required by the Technical Specifications.
In the event of an inoperable PASS during accident conditions, the alternate preplanned method for assessing core damage is Plant Procedure (PPM)9,3.22."Core Damage Evaluation." Included in this procedure are evaluations of water level history, installed radiation monitor indication and hydrogen content in the containment atmosphere.
Regarding restoring the system to operable status, Maintenance Work Requests-(HWRs)have been prepared to repair PASS Containment Isolation Valves PSR-V-X77A/1, A2, A3 and A4.Current plans are to repair the valves during the next maintenance and refueling outage (Spring 1990).Very truly yours, i'.u(/)..~C.H.Powers (H/D 927M)WNP-2 Plant Manager CHP:lr cc: Hr.C.J.Bosted, NRC Site (H/0 901A)Hs.Dottie Sherman, ANI Hr.D.L.Williams, BPA (H/D 399)Document Control Desk, NRC