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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARGO2-98-111, 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 GO2-98-006, 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%1998-01-14014 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% GO2-97-068, Ro:On 970327,reactor Scrammed.Evaluation Results,Conclusions & Corrective Actions Will Be Shared W/Nrc Prior to Plant Startup from Maint & Refueling Outage1997-04-0909 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 GO2-96-221, 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 Generated1996-11-0808 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 GO2-95-238, 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 Refurbishment1995-11-0808 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 GO2-95-156, 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 Work1995-08-18018 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 GO2-95-053, 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 9503141995-03-16016 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 GO2-94-223, 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 Removed1994-09-26026 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 GO2-93-293, 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 Necessary1993-12-17017 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 GO2-93-290, 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 Progress1993-12-10010 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 GO2-93-156, 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 9306071993-06-11011 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 GO2-93-012, 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 Channels1993-01-11011 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 GO2-92-234, 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 Channel1992-10-0707 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 GO2-92-129, 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 Startup1992-05-22022 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 GO2-91-135, 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 Operational1991-07-15015 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 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 GO2-84-528, RO Re Use of Fan Motor W/O Performing Seismic Qualification. Caused by Motor Failure on Fan WWA-FN-53A.Motor to Be Reinstalled,Qualification Obtained & Spare Motor Ordered1984-10-0202 October 1984 RO Re Use of Fan Motor W/O Performing Seismic Qualification. Caused by Motor Failure on Fan WWA-FN-53A.Motor to Be Reinstalled,Qualification Obtained & Spare Motor Ordered ML20090B2281984-07-0606 July 1984 Ro:On 840602,w/reactor Operating in Mode 1,increase in Coolant Conductivity Noted & Measures Taken to Reduce Levels.Caused by Steam Impingement.Condenser Repaired. Preparations Made for Startup 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 ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr 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 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 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
ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr 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 ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr 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 ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr 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 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 ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr 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 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. 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 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 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 GO2-99-041, WNP-2 1998 Annual Operating Rept. with1998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with 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 ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr 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 ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr 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 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 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-1998-013, :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
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
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 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
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 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 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 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 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 1999-09-30
[Table view] |
Text
ACCELERATED DI BUTION DEMON STRA,TIO.'i SYSTEM REGULA I ZNEORilATZON DZSTRISUTIOiZSTEN (RIDE)
ACCESSION NBR:8903090053 DOC.DATE: 89/02/16 NOTARIZED:
NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION POWERiC.M.
Washington Public Power Supply System RECIP. NAME RECIPIENT AFFILIATION MARTIN,J.B.
Region 5, Ofc of the Director
SUBJECT:
Special rept re post-accident sampling containment atmosphere radiation monitor.
DISTRIBUTiON CODE:
IE22D COPIES RECEIVED:LTR t
ENCL J SIZE:
TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
RECIPIENT ID CODE/NAME PD5 LA SAMWORTH,R INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB ARM/DCTS/DAB NRR/DEST/ADE SH NRR/DEST/CEB SH NRR/DEST/ICSB 7
NRR/DEST/MTB 9H NRR/DEST/RSB SE NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NRR/DREP/RPB 10 NUDOCS-ABSTRACT RES/DSIR/EIB RGN5 FILE 01 EXTERNAL: EG&G WILLIAMSiS H
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LTTR 45 ENCL 44
@~i WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968
~ 3000 George Washington Way
~ Richland, Washington 99362
'l
'.c Docket No. 50-397 February 16, 1989 Nr. J.B. Martin Regional Administrator
- USNRC, Region V
1450 Maria Lane, Suite 210 Walnut Creek, CA 94596 Dear Nr. Martin;
Subject:
NUCLEAR PLANT NO.
2 LICENSE NO.
NPF-21 SPECIAL REPORT:
POST-ACCIDENT SAMPLING CONTAINMENT ATMOSPHERE RADIATION MONITOR This special report is submitted pursuant to the requirements of WNP-2 Technical Specification Table 3;3.7.5-1 (Instrument No. 24:
Post Accident Sampling Containment Atmospheric Radiation Monitor), Action Statement 81
~
Action Statement Bl 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 action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status."
id" gib 53 890 0397 890309o0cy, 050oPNU
>9 6
On february 3, 1989 during an E'mergency Preparedness Drill, Plant personnel were unable to obtain a sample from the Post Accident Sampling System (PASS).
Accordingly, a Maintenance Work Request (NMR) was written to Lrouble shoot the problem.
During the trouble shooting eFforts it was discovered that vacuum pump PSR-P-702 (Suppression Pool Atmospheric Sample Return) would run freely but there was no.compression.
The problem is suspected to be a broken pump shaft.
As a result, the system was inoperable and Post Accident Sampling Containment Atmospheric Radiation NoniLor PSR-RI-704 was not able to perform its function as required by the Technical Specifications.
In the event. of an inoperable PASS during accident conditions, the alternate method for assessing core damage is Plant. Procedure (PPN) 9.3.22, "Core Damage Evaluation."
Included in this procedure are evaluations oF water level history, installed monitor indication and hydrogen conLent in the containment atmospheres Regarding restoring the system to operable
- status, replacement parts for PSR-P-702 are currently on order and the pump will be repaired as soon as possible (estimated completion date is April-Nay, 1989).
As part of the repair effort, an evaluation of the failure mode will be performed and the results provided in a supplemental report.
Very truly yours, C.
Powers (N/0 927M)
NNP-2 Plant Manager cc:
Mr. C.J.
- Bosted, NRC Site (N/0 901A)
Ns. Dottie Sherman, AN1 Nr. O.L. Williams, BPA (M/0 399)
~,