LER-1988-032, Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed |
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION g
- j WASHINGTON. D. C. 20555 g,*...*/
JUN 161989 C. J. Lovell EG&G Idaho, Inc.
MS 2407 P. O. Box 1625 Idaho Falls, ID 83415-2407 W. P. Poore Nuclear Operations Analysis Center Building 9201-3 MS-8065 Oak Ridge National Laboratory P. O. Box 2009 Oak Ridge, TN 37831 RESOLUTION OF LERs MISSING FROM LERTRK/SCSS/DCS
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Ref: Letter from C. J. Lovell to W. P. Poore, First Ouarter 1989 LERTRK/SCSS Ouality Assurance Check - CJL-5-89, April 20,1989.
The referenced letter contained a listing of sequence numbers of Licensee Event Repons (LERs) that were missing form the 1988 INEL datafile, SCSS, and NRC DCS. I have reviewed this list and have been able to resolve all of the missing items.
Several of the LERs had been issued but somehow never got into the NRC document system for distribution and inclusion onto DCS. Copies of these LERs are enclosed. They include the following event reports:
LERs THAT HAVE BEEN ISSUED AND ARE ENCLOSED 25488011 33888021 26588010 41288018 26588022 41488002 27588029 41488004 30488015 Some of the nissing reports have just been issued. They have been received and distributed by the NRC. Copies of these LERs are not enclosed. They include:
8906290317 890616
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PDR ADOCK 05000219 S
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LERs THAT HAVE JUST BEEN RECEIVED UNDER NORMAL DCS DISTRIBUTION AND ARE NOT ENCLOSED 27788027 31388023 J
31388019 35488014 31388020 36888020 i
31388022 52888023
~ Another gmuping of_ missing LERs were associated with 50.72 repons which were subsequently determined to not be reponable as 50.73 repons.. Instead of reassigning the LER number to a reponable event, the licensees simply cancelled the repon and did not reuse the sequence number. The cancelled sequence numbers include:
LERs THAT WERE CANCRT Trn AND WILL NOT BE ISSUED.
21988025 33188014 N 1988032 34488034 25088031 34488038 28088047 34488048 28288012 41288014 32388017 52988016 Finally, two special cases were discovered. These involved H.'B. Robinson and Bmwns Ferry. Discussions of these cases follow.
SPECIAL CASES H. B. Robinson 2 handles their security event repons differently than other licensees. In their case, they issue their security event repons on an LER form but the number assigned on the form is a sequence series that begins with an S (e.g., 88-S01, 88-S02). This method is in agreement with all other licensees. However, H.B. Robinson also assigns a standard LER sequence number to these security event repons. This sequence number is assigned and tracked internally and is only included, if at all, for information on the transmittal let:er of the security event repon. Thus, only persons who received security event repons from the DCS would know about these corresponding regular sequence numbers. For 198F, 'i. B. Robinson issued five such security repons, numbers S01 through S05. The normal LER sequence number assigned to these repons are as follows:
H. B. ROBINSON SECURITY REPORT /LER SEQUENCE NUMBERS S01 26188004 SO2 26188016 S03 26188025 SO4 261880.29 S05 26188030 2
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Browns Ferry issued LER 26088050. Previous discussions with the licensee indicated that this number was in error in that it was truly a Unit 2 event but the sequence number given was for Unit 1. To ' correct this error, a revision would be forthcoming reassigning this LER as 26088019. This revision has yet to be received. I contacted the licensee again and was informed that 26088019 is still to be issued but extensive reanalysis of corrective actions which will be incorporated into the LER have yet to be completed. No firm date of issuance could therefore be given. In addition, it was noted that the original transmittal letter for this revision would indicate that LER number 25988050 would not be used.
Thus, LER 25988050 should be listed as being "Not Issued" and, once the revision LER 26088019 is issued, the present hole of LERs from 26088019 through 26088049 should be removed with LER 28088019 being the final LER in numeric sequence for Unit 2.
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. Based on these clarifications, the highest LER sequence number that will be used in 1988 at each of the plants is listed in the table on the following page. Both LERTRK and the inventory file for SCSS should contain information pertinent to all report sequence numbers from 88001 through these highest numbers. As always, additional LERs may subsequently be submitted, but their sequence numbers should only add to this listing.
If you have any questions, please contact me.
Sincerely, WW&bY Thomas R. Wolf enclosure cc w/ enclosure NRC Document Control Branch cc w/o enclosure RLDennig 1
JLCrooks MHWilliams l
JCRosenthal
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b lr HIGHEST LER SEQUENCE NUMBER
- - 02988015 27888011 32488021 38888016 13388002 28088048 32588035 38988004 15588009 28188025 32788047 39588015 2M88021 28288013 32888041 39788038 21388023.
28588038 33188019 40088035 21988035 28688010' 33388014 40988002 22088021 28788006 33488016 41088068 23788023 28988006 33588008 41288020 24488010 29388027 33688011 41388027 24588013 29588024 33888028 41488033 24788020 29688008 33988019 41688020 24988018 29888027
'34188037 42388028 25088032 30188003 34488049 42488045 25188012 30288028 34688029 44088047 25488016 30488018 34888024 44388010 25588025 30588013 35283043 45488011 25988053
'30688002' 35488036 45588012 26088019' 30988011 36188036' 45688026 261880302 31188026 36288012 45788032 26388008 31288021 36488010 45888029 26588030 31388025 36688025 46188032 26688010 31588014 36888022' 48288029 26788018 31688011 36988049' 48388015 26988014 31788015 37088013 49888066 27088003 31888006 37388029 49988001 27188015 32088011-37488017 52888026
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27288020 32188019 38288034 52988017
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27588032 32288019 38788024 53088008 27788033 32388026
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l 2 See "Special Case" discussion on Browns Ferry. Assumes LER 26088050 will be
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reissued as 26088019.
- See "Special Case" discussion on H. B. Robinson.
5 Indian Point 3 LER 28688010 is a " Safeguards Event Repon" only.
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' Reflects recent LERs just received through normal DCS distribution. Copies of these LERs are not included.
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| 05000219/LER-1988-001-01, :on 880106,unusual Instrument Indications on Shutdown Cooling Sys & Reactor Recirculation Pump Seal Pressure Noted.Caused by Heating Sys Out of Svc,Low Temp & Personnel Insensitivity to Bldg Temp |
- on 880106,unusual Instrument Indications on Shutdown Cooling Sys & Reactor Recirculation Pump Seal Pressure Noted.Caused by Heating Sys Out of Svc,Low Temp & Personnel Insensitivity to Bldg Temp
| 10 CFR 50.73(a)(2)(vii)(8) | | 05000219/LER-1988-002-01, :on 880128,containment Radiation Monitoring Sys Determined to Be Left out-of-spec from 861119 Until 871109. Caused by Unclear Info for Testing in Vendor Instruction Manual.Monitors Repaired & Retested |
- on 880128,containment Radiation Monitoring Sys Determined to Be Left out-of-spec from 861119 Until 871109. Caused by Unclear Info for Testing in Vendor Instruction Manual.Monitors Repaired & Retested
| 10 CFR 50.73(a)(2)(1) | | 05000219/LER-1988-003-01, :on 880520,discovered That Containment Particulate Monitor Sample Line Isolation Valve Control Circuitry Does Not Meet Single Failure Criteria.Caused by Design Deficiency.Direction Provided |
- on 880520,discovered That Containment Particulate Monitor Sample Line Isolation Valve Control Circuitry Does Not Meet Single Failure Criteria.Caused by Design Deficiency.Direction Provided
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000219/LER-1988-004-01, :on 880229,isolation Condenser Actuation Pressure Sensors Exceeded Setpoint Limit.Caused by Inadequate Instrument Repeatability.Pressure Sensors Adjusted within Desired Setpoint |
- on 880229,isolation Condenser Actuation Pressure Sensors Exceeded Setpoint Limit.Caused by Inadequate Instrument Repeatability.Pressure Sensors Adjusted within Desired Setpoint
| 10 CFR 50.73(a)(2)(1) | | 05000219/LER-1988-005, :on 880324,discovered That Tagging Error Caused Components of Both Standby Gas Treatment Sys to Be Inoperable.Caused by Personnel Error.Event Reviewed W/All Operations Personnel |
- on 880324,discovered That Tagging Error Caused Components of Both Standby Gas Treatment Sys to Be Inoperable.Caused by Personnel Error.Event Reviewed W/All Operations Personnel
| 10 CFR 50.73(a)(2)(B) | | 05000219/LER-1988-006, :on 880325,four Isolation Condenser Pipe Break Sensors Tripped.Caused by Past Mod & Switch Problems. Switches Adjusted within Tech Spec Limits & Four Reactor Protection Sys Digital Sensors to Be Replaced |
- on 880325,four Isolation Condenser Pipe Break Sensors Tripped.Caused by Past Mod & Switch Problems. Switches Adjusted within Tech Spec Limits & Four Reactor Protection Sys Digital Sensors to Be Replaced
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000219/LER-1988-007, :on 880412,inadequate Support of Reactor Sample Line Containing Containment Isolation Valve Determined. Caused by Personnel Error.Sample Line Declared Inoperable & Isolated.Addl Supports Designed |
- on 880412,inadequate Support of Reactor Sample Line Containing Containment Isolation Valve Determined. Caused by Personnel Error.Sample Line Declared Inoperable & Isolated.Addl Supports Designed
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000219/LER-1988-008, :on 880414,reactor Bldg Isolation & Standby Gas Treatment Sys Automatic Initiation Occurred.Caused by Personnel Error.Emergency Operating Procedures Entered for Secondary Containment Control |
- on 880414,reactor Bldg Isolation & Standby Gas Treatment Sys Automatic Initiation Occurred.Caused by Personnel Error.Emergency Operating Procedures Entered for Secondary Containment Control
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000219/LER-1988-009-01, :on 880602,isolation Condenser Automatic Actuation Pressure Sensors RE15A & RE15C Tripped at Values Greater than Tech Spec 2.3.E.Caused by Inadequate Instrument Repeatability.Pressure Sensors Adjusted |
- on 880602,isolation Condenser Automatic Actuation Pressure Sensors RE15A & RE15C Tripped at Values Greater than Tech Spec 2.3.E.Caused by Inadequate Instrument Repeatability.Pressure Sensors Adjusted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000219/LER-1988-010, :on 880601,standby Gas Treatment Sys Manually Initiated Due to Rising Radiation Levels.Caused by Personnel Error.Personnel Counselled,Operating Procedure Rev Completed & Min Sump Level Raised to Increase Pressure |
- on 880601,standby Gas Treatment Sys Manually Initiated Due to Rising Radiation Levels.Caused by Personnel Error.Personnel Counselled,Operating Procedure Rev Completed & Min Sump Level Raised to Increase Pressure
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000219/LER-1988-011, :on 880622,containment Spray Inappropriately Returned to Svc Due to Improperly Performed Surveillance Test.Caused by Instrument Line Configuration Being Complexed & Inadequately Labeled |
- on 880622,containment Spray Inappropriately Returned to Svc Due to Improperly Performed Surveillance Test.Caused by Instrument Line Configuration Being Complexed & Inadequately Labeled
| | | 05000219/LER-1988-012, :on 880707,discovered That Control Circuitry for Four Electromatic Relief Valves & Two RWCU Sys Valves Did Not Meet 10CFR50,App R Criteria.Caused by Design Deficiency.Fire Watch Posted |
- on 880707,discovered That Control Circuitry for Four Electromatic Relief Valves & Two RWCU Sys Valves Did Not Meet 10CFR50,App R Criteria.Caused by Design Deficiency.Fire Watch Posted
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000219/LER-1988-014, :on 880721,upstream MSIV in Steam Line a Failed Surveillance Test & Declared Inoperable.Caused by Procedural Inadequacy.Damage to Guide Ribs Repaired & Poppet Properly Aligned W/Guide Ribs.Valve Stem Replaced |
- on 880721,upstream MSIV in Steam Line a Failed Surveillance Test & Declared Inoperable.Caused by Procedural Inadequacy.Damage to Guide Ribs Repaired & Poppet Properly Aligned W/Guide Ribs.Valve Stem Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) | | 05000219/LER-1988-015, :on 880805,reactor Isolation Signal Inadvertently Initiated During Intermediate Range Neutron Monitor Front Panel Surveillance.Caused by Circuit Not Configured to Facilitate Testing.Fuse Replaced |
- on 880805,reactor Isolation Signal Inadvertently Initiated During Intermediate Range Neutron Monitor Front Panel Surveillance.Caused by Circuit Not Configured to Facilitate Testing.Fuse Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000219/LER-1988-016, :on 880819,isolation Condenser Automatic Actuation Pressure Sensors RE15A,RE15B,RE15C & RE15D Tripped at Values Greater than Specified in Tech Spec 2.3.E.Caused by Inadequate Instrument Repeatability |
- on 880819,isolation Condenser Automatic Actuation Pressure Sensors RE15A,RE15B,RE15C & RE15D Tripped at Values Greater than Specified in Tech Spec 2.3.E.Caused by Inadequate Instrument Repeatability
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000219/LER-1988-017, :on 880822,three Control Rod Low Accumulator Pressure Alarms Present for More than 1 H.Caused by Operator Failing to Recharge Accumulators in Accordance W/Procedures. Accumulators Recharged & Operators Counseled |
- on 880822,three Control Rod Low Accumulator Pressure Alarms Present for More than 1 H.Caused by Operator Failing to Recharge Accumulators in Accordance W/Procedures. Accumulators Recharged & Operators Counseled
| | | 05000219/LER-1988-018, :on 880828,isolation Condenser Sys B Actuated During Valve Operability Test When Control Room Operator Inadvertently Opened Wrong Valve.Caused by Lack of Operator Attention.Operator Counseled |
- on 880828,isolation Condenser Sys B Actuated During Valve Operability Test When Control Room Operator Inadvertently Opened Wrong Valve.Caused by Lack of Operator Attention.Operator Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000219/LER-1988-019, :on 880902,discovered That Isolation Condenser Vent Line Inboard Manual Isolation Valve a in Closed Position.Caused by Procedural Inadequacy.Valve Opened & Full Sys Lineups Performed |
- on 880902,discovered That Isolation Condenser Vent Line Inboard Manual Isolation Valve a in Closed Position.Caused by Procedural Inadequacy.Valve Opened & Full Sys Lineups Performed
| 10 CFR 50.73(a)(2)(B) | | 05000219/LER-1988-020, :on 880908,isolation Condenser Vent Radiation & Emergency Svc Water Monitors Incapable of Leak Detection. Caused by Design Deficiency Due to Failure to Properly Evaluate Potential Area Radiation Conditions |
- on 880908,isolation Condenser Vent Radiation & Emergency Svc Water Monitors Incapable of Leak Detection. Caused by Design Deficiency Due to Failure to Properly Evaluate Potential Area Radiation Conditions
| 10 CFR 50.73(a)(2) | | 05000219/LER-1988-022, :on 881002,power to 4,160 Volt Bus 1D Was Lost When Breaker 1D Tripped & Locked Out Due to Ground Fault. Caused by Isolated Defect in Cable Insulation.Cable Replaced |
- on 881002,power to 4,160 Volt Bus 1D Was Lost When Breaker 1D Tripped & Locked Out Due to Ground Fault. Caused by Isolated Defect in Cable Insulation.Cable Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000219/LER-1988-023, :on 880927,drywell Airlock Door Leak Rate Not Tested at Frequency or Test Pressure Required by 10CFR50, App J.Caused by Insufficient Administrative Controls.Tech Spec Change Under Review |
- on 880927,drywell Airlock Door Leak Rate Not Tested at Frequency or Test Pressure Required by 10CFR50, App J.Caused by Insufficient Administrative Controls.Tech Spec Change Under Review
| | | 05000219/LER-1988-024, :on 881005,MSIV Closure Signal Occurred During Intermediate Range Neutron Monitor (IRM) Front Panel Surveillance Test.Caused by Procedural Inadequacy.Irm Bench Calibr Procedure Revised |
- on 881005,MSIV Closure Signal Occurred During Intermediate Range Neutron Monitor (IRM) Front Panel Surveillance Test.Caused by Procedural Inadequacy.Irm Bench Calibr Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000219/LER-1988-025, Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed | Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed | | | 05000219/LER-1988-026, :on 881019,reactor Scram Signal Received While Shut Down During Surveillance Testing.Caused by Inadequate Procedure.Procedure Will Be Revised & LER Will Be Made Required Reading for All Qualified Reviewers |
- on 881019,reactor Scram Signal Received While Shut Down During Surveillance Testing.Caused by Inadequate Procedure.Procedure Will Be Revised & LER Will Be Made Required Reading for All Qualified Reviewers
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000219/LER-1988-027, :on 881022,fire Watch Required by Tech Specs Missed Due to Inadequate Guidance to Temporary Employees. Caused by Inadequate Guidance & Direction Being Provided to Temporary Contractor Employees |
- on 881022,fire Watch Required by Tech Specs Missed Due to Inadequate Guidance to Temporary Employees. Caused by Inadequate Guidance & Direction Being Provided to Temporary Contractor Employees
| 10 CFR 50.73(a)(2)(1) | | 05000219/LER-1988-029, :on 881024,containment Isolation Valves V-38-9, 10,16,17,22 & 23 Failed to Meet NUREG-0737 Design Criterion. Caused by Personnel Error.Mod of Subj Valves Planned |
- on 881024,containment Isolation Valves V-38-9, 10,16,17,22 & 23 Failed to Meet NUREG-0737 Design Criterion. Caused by Personnel Error.Mod of Subj Valves Planned
| 10 CFR 50.73(a)(2) | | 05000219/LER-1988-032, Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed | Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed | |
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