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| | issue date = 09/14/1989 | | | issue date = 09/14/1989 |
| | title = Special Rept:On 890821,leakage Discovered in post-accident Sampling Sys Containment Valves When in Closed Position. Maint Work Requests Prepared to Repair post-accident Sampling Sys Containment Isolation Valves | | | title = Special Rept:On 890821,leakage Discovered in post-accident Sampling Sys Containment Valves When in Closed Position. Maint Work Requests Prepared to Repair post-accident Sampling Sys Containment Isolation Valves |
| | author name = POWERS C M | | | author name = Powers C |
| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| | addressee name = MARTIN J B | | | addressee name = Martin J |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) | | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| | docket = 05000397 | | | docket = 05000397 |
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| =Text= | | =Text= |
| {{#Wiki_filter:<CCELERATED DlgR1BU'TlON DEMONST+TlON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8909250014 DOC.DATE: 89/09/14.NOTARIZED: | | {{#Wiki_filter:<CCELERATED DlgR1BU'TlON DEMONST+TlON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO FACIAL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION POWERS,C.M. | | ACCESSION NBR:8909250014 DOC.DATE: 89/09/14. NOTARIZED: NO DOCKET I FACIAL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION POWERS,C.M. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION I MARTIN,J.B. Region 5, Ofc of the Director ' |
| Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION MARTIN,J.B. | | R |
| Region 5, Ofc of the Director | |
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| ==SUBJECT:== | | ==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 ALL''RIBS" RECIPIIRIS: | | Special rept:on 890821,post-accident sampling primary coolant radiation monitor. |
| ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP
| | DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR |
| " 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
| | 'TITLE: 50.73/50.9 Licensee Event Report (LER), |
| %M%5 ENCL~0
| | NOTES: |
| | JIncident ENCL / SIZE Rpt, etc. D ' |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR EN CL ID CODE/NAME LTTR ENCL PD5 LA 1 PD5 PD SAMWORTH,R 1 INTERNAL: ACRS MICHELSON ACRS MOELLER ACRS WYLIE AEOD/DOA AEOD/DSP/TPAB AEOD/ROAB/DSP " |
| | DEDRO IRM/DCTS/DAB NRR/DEST/CEB 8H NRR/DEST/ESB 8D NRR/DEST/ICSB 7 NRR/DEST/MEB 9H NRR/DEST/MTB 9H NRR/DEST/PSB 8D NRR/DEST/RSB 8E NRR/DEST/SGB 8D NRR/DLPQ/HFB 10 NRR/DLPQ/PEB 10 NRR/DOEA/EAB 11 NRRtBBB RPB 10 NUDOCS-ABSTRACT EG FILE 02 RES/DSIR/EIB RGN5 LE Ol EXTERNAL: EG&G WILLIAMS,S L ST LOBBY WARD LPDR NRC PDR NSIC MAYS,G NSIC MURPHYIG A~ |
| | NUDOCS FULL TXT 8 I |
| | D D |
| | D NOZE 'IO ALL ''RIBS" RECIPIIRIS: |
| | S PIZASE HELP US 'IO REEVE HASTE! CGHIMT 'IHE DOI.'X3KKI'KNIBOLDESK, TOTAL NUMBER %PVOVRP%+%%8P %M %5 ENCL ~ |
| | RXM Pl-37 (EXT. 20079) K) EEiZKMQR KXK NAKE FR% DIBTRZBUZICN 0 |
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| 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 | | 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 |
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| ==Dear Mr.Martin:== | | ==Dear Mr. Martin:== |
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| ==Subject:== | | ==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
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| '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 hours, 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."
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| 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). | | nicall 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-Specification Table 3.3.7. 5-1 ( Instrument 'o. 29: Post-Accident Sampling Primary Coolant Radiation Monitor), Action Statement 81. |
| 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. | | 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 hours, or: |
| 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. | | (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." |
| 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}} | | |
| | 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}} |
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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
ML17292B2281998-01-14014 January 1998
Informs of Unexpected Change in Feedwater Temperature & Flow Indication Used to Calculate Plant Heat Balance During Routine Trending of Plant Computer Feedwater Temperatures on 980112.Corrective Actions Reduced Reactor Power to 99%
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
ML17292A5901996-11-0808 November 1996
Special Rept:On 961023,intermediate & High Range Stack Monitors PRM-RE-1B & PRM-RE-1C Declared Inoperable.Caused by Monitor Output Had Upward Trend Due to Electronic Noise Interference.Work Request Generated
ML17291B0981995-11-0808 November 1995
Special Rept:On 951026,RB Effluent Monitoring Sys Inoperable for 72 H Due to Failure of Mid Range Stack Monitor.Cryostat Cooling Assemblies for Mid & High Range Stack Monitors Returned to Vendor for Refurbishment
ML17291A9781995-08-18018 August 1995
Special Rept:On 950712,loose Part Detection Sys Channel 4 Failed Due to Electrical Noise During Daily Check.Channel 4 Will Remain Inoperable Until Next Forced or Scheduled Outage When Primary Containment de-inerted for Other Work
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
ML17291A4131994-09-26026 September 1994
Special Rept:On 940825,loose Part Detection Sys Channel Number Eight Actuated Associated MCR Alarm & on 940908 Subj Channel Began Alarming Due to Electronic Noise Originating in Drywell.Electronic Module of Channel Removed
ML17290A8871993-12-17017 December 1993
Special Rept:On 931116,loose Parts Detection Sys Channel 5 Did Not Pass Daily Channel Surveillance.Exact Cause Not Determined.Need to Provide Addl Notifications Should Other Channels Become Inoperable Not Necessary
ML17290A8381993-12-10010 December 1993
Special Rept:On 931126,main Control Room Received Stack Monitor Sys Trouble Annunciator & Status Display Indicated High Range Channel Failed self-test.Caused by Component Failure of Stack Monitor Detector.Replacement in Progress
ML17290A5301993-06-11011 June 1993
Special Rept:On 930503,space Frame & Attached Seismic Triaxial Peak Accelorograph (SEIS-TPA-1) Removed to Allow for Refueling of Reactor Core.Instrument Returned to Svc on 930607
ML17289B1281993-01-11011 January 1993
Update to 921007 Special Rept Re Inoperability of Loose Parts Detection Instrumentation Following Failure of Channel 1 on 921113.On 921128,constant Alarm Received on Channel 8. Maint Work Request Initiated to Repair Failed Channels
ML17289A9161992-10-0707 October 1992
Special Rept:On 920905,channel 1 on Main Steam Line D Nozzle in Drywell Did Not Pass Surveillance & Inoperable for More than 30 Days.Caused by Faulty Equipment in Drywell. Maint Work Request Initiated to Repair Failed Channel
ML17289A6001992-05-22022 May 1992
Special Rept:On 920420,seismic Triaxial Peak Accelerograph & Space Frame Removed to Allow Refueling of Reactor Core. Accelerometer Will Be Returned to Svc When Space Frame Reattached to Reactor Vessel Prior to Startup
ML17286A9401991-07-15015 July 1991
Special Rept:On 910604,time History Triaxial Acceleration Sensor Found Malfunctioning During Performance of Seismic Sys Maint Activities.Failed Unit Returned Under Warranty to Supplier for Repair.Sys Now Fully Operational
ML17285A8001989-10-19019 October 1989
Special Rept:On 891009,valve PSR-V-104 Isolated to Repair Leaking PASS Sample Valve PSR-V-616,resulting in PASS Being Inoperable.Plan Made to Replace Valve PSR-V-616 to Restore Sys by Jan 1990
ML17285A7331989-09-14014 September 1989
Special Rept:On 890821,leakage Discovered in post-accident Sampling Sys Containment Valves When in Closed Position. Maint Work Requests Prepared to Repair post-accident Sampling Sys Containment Isolation Valves
ML17285A3511989-03-22022 March 1989
Special Rept:On 890306,post-accident Sampling Primary Coolant Radiation Monitor Inoperable.Caused by Excess Moisture.Pass Vacuum Pump PSR-P-702 Replaced W/New Pump & Bulkhead Fitting Repaired
ML17285A2931989-02-16016 February 1989
Special Rept:On 890203,plant Personnel Unable to Obtain Sample from PASS Due to Lack of Compression in Vacuum Pump. Caused by Broken Pump Shaft.Replacement Parts Currently on Order & Pump Will Be Repaired as Soon as Possible
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
ML17292B2281998-01-14014 January 1998
Informs of Unexpected Change in Feedwater Temperature & Flow Indication Used to Calculate Plant Heat Balance During Routine Trending of Plant Computer Feedwater Temperatures on 980112.Corrective Actions Reduced Reactor Power to 99%
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
ML17292A5901996-11-0808 November 1996
Special Rept:On 961023,intermediate & High Range Stack Monitors PRM-RE-1B & PRM-RE-1C Declared Inoperable.Caused by Monitor Output Had Upward Trend Due to Electronic Noise Interference.Work Request Generated
ML17291B0981995-11-0808 November 1995
Special Rept:On 951026,RB Effluent Monitoring Sys Inoperable for 72 H Due to Failure of Mid Range Stack Monitor.Cryostat Cooling Assemblies for Mid & High Range Stack Monitors Returned to Vendor for Refurbishment
ML17291A9781995-08-18018 August 1995
Special Rept:On 950712,loose Part Detection Sys Channel 4 Failed Due to Electrical Noise During Daily Check.Channel 4 Will Remain Inoperable Until Next Forced or Scheduled Outage When Primary Containment de-inerted for Other Work
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
ML17291A4131994-09-26026 September 1994
Special Rept:On 940825,loose Part Detection Sys Channel Number Eight Actuated Associated MCR Alarm & on 940908 Subj Channel Began Alarming Due to Electronic Noise Originating in Drywell.Electronic Module of Channel Removed
ML17290A8871993-12-17017 December 1993
Special Rept:On 931116,loose Parts Detection Sys Channel 5 Did Not Pass Daily Channel Surveillance.Exact Cause Not Determined.Need to Provide Addl Notifications Should Other Channels Become Inoperable Not Necessary
ML17290A8381993-12-10010 December 1993
Special Rept:On 931126,main Control Room Received Stack Monitor Sys Trouble Annunciator & Status Display Indicated High Range Channel Failed self-test.Caused by Component Failure of Stack Monitor Detector.Replacement in Progress
ML17290A5301993-06-11011 June 1993
Special Rept:On 930503,space Frame & Attached Seismic Triaxial Peak Accelorograph (SEIS-TPA-1) Removed to Allow for Refueling of Reactor Core.Instrument Returned to Svc on 930607
ML17289B1281993-01-11011 January 1993
Update to 921007 Special Rept Re Inoperability of Loose Parts Detection Instrumentation Following Failure of Channel 1 on 921113.On 921128,constant Alarm Received on Channel 8. Maint Work Request Initiated to Repair Failed Channels
ML17289A9161992-10-0707 October 1992
Special Rept:On 920905,channel 1 on Main Steam Line D Nozzle in Drywell Did Not Pass Surveillance & Inoperable for More than 30 Days.Caused by Faulty Equipment in Drywell. Maint Work Request Initiated to Repair Failed Channel
ML17289A6001992-05-22022 May 1992
Special Rept:On 920420,seismic Triaxial Peak Accelerograph & Space Frame Removed to Allow Refueling of Reactor Core. Accelerometer Will Be Returned to Svc When Space Frame Reattached to Reactor Vessel Prior to Startup
ML17286A9401991-07-15015 July 1991
Special Rept:On 910604,time History Triaxial Acceleration Sensor Found Malfunctioning During Performance of Seismic Sys Maint Activities.Failed Unit Returned Under Warranty to Supplier for Repair.Sys Now Fully Operational
ML17285A8001989-10-19019 October 1989
Special Rept:On 891009,valve PSR-V-104 Isolated to Repair Leaking PASS Sample Valve PSR-V-616,resulting in PASS Being Inoperable.Plan Made to Replace Valve PSR-V-616 to Restore Sys by Jan 1990
ML17285A7331989-09-14014 September 1989
Special Rept:On 890821,leakage Discovered in post-accident Sampling Sys Containment Valves When in Closed Position. Maint Work Requests Prepared to Repair post-accident Sampling Sys Containment Isolation Valves
ML17285A3511989-03-22022 March 1989
Special Rept:On 890306,post-accident Sampling Primary Coolant Radiation Monitor Inoperable.Caused by Excess Moisture.Pass Vacuum Pump PSR-P-702 Replaced W/New Pump & Bulkhead Fitting Repaired
ML17285A2931989-02-16016 February 1989
Special Rept:On 890203,plant Personnel Unable to Obtain Sample from PASS Due to Lack of Compression in Vacuum Pump. Caused by Broken Pump Shaft.Replacement Parts Currently on Order & Pump Will Be Repaired as Soon as Possible
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
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
[Table view] |
Text
<CCELERATED DlgR1BU'TlON DEMONST+TlON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8909250014 DOC.DATE: 89/09/14. NOTARIZED: NO DOCKET I FACIAL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION POWERS,C.M. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION I MARTIN,J.B. Region 5, Ofc of the Director '
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SUBJECT:
Special rept:on 890821,post-accident sampling primary coolant radiation monitor.
DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR
'TITLE: 50.73/50.9 Licensee Event Report (LER),
NOTES:
JIncident ENCL / SIZE Rpt, etc. D '
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR EN CL ID CODE/NAME LTTR ENCL PD5 LA 1 PD5 PD SAMWORTH,R 1 INTERNAL: ACRS MICHELSON ACRS MOELLER ACRS WYLIE AEOD/DOA AEOD/DSP/TPAB AEOD/ROAB/DSP "
DEDRO IRM/DCTS/DAB NRR/DEST/CEB 8H NRR/DEST/ESB 8D NRR/DEST/ICSB 7 NRR/DEST/MEB 9H NRR/DEST/MTB 9H NRR/DEST/PSB 8D NRR/DEST/RSB 8E NRR/DEST/SGB 8D NRR/DLPQ/HFB 10 NRR/DLPQ/PEB 10 NRR/DOEA/EAB 11 NRRtBBB RPB 10 NUDOCS-ABSTRACT EG FILE 02 RES/DSIR/EIB RGN5 LE Ol EXTERNAL: EG&G WILLIAMS,S L ST LOBBY WARD LPDR NRC PDR NSIC MAYS,G NSIC MURPHYIG A~
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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:
nicall 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-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
