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| | Docket = 05000320 | | | Docket = 05000320 |
| | LER year = 2098 | | | LER year = 1998 |
| | LER number = 1 | | | LER number = 1 |
| | LER revision = | | | LER revision = 0 |
| | Event date = | | | Event date = |
| | Report date = | | | Report date = |
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| l GPU Nuclear,Inc. | | l GPU Nuclear,Inc. |
| ( Route 441 South l NUCLEAR P**' **'i c | | ( |
| | Route 441 South l |
| | NUCLEAR P**' **'i c |
| * B ** *** | | * B ** *** |
| Middletown, PA 17057-0480 Tel 717-944-7621 July 02,1998 1920-98-20355 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 | | Middletown, PA 17057-0480 Tel 717-944-7621 July 02,1998 1920-98-20355 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 |
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| ==Dear Sir:== | | ==Dear Sir:== |
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| ==Subject:== | | ==Subject:== |
| Three Mile Island Nuclear Station, Unit 2 (TMI-2) | | Three Mile Island Nuclear Station, Unit 2 (TMI-2) |
| Possescion Only License No. DPR-73 Docket No. 50-320 LER 98-001-00, " Flood Barriers Breached Between the Turbine Building and the Control Building Area Due to Inadequate Fieldwork Documents" This letter transmits Licensee Event Report (LER) number 98-001-00 cencerning :. condition which | | Possescion Only License No. DPR-73 Docket No. 50-320 LER 98-001-00, " Flood Barriers Breached Between the Turbine Building and the Control Building Area Due to Inadequate Fieldwork Documents" This letter transmits Licensee Event Report (LER) number 98-001-00 cencerning :. condition which |
| . was evaluated and determined to be reportable on June 15,1998.
| | . was evaluated and determined to be reportable on June 15,1998. |
| This LER is being submitted pursuant to 10 CFR 50.73, using the required NRC forms (attached). | | This LER is being submitted pursuant to 10 CFR 50.73, using the required NRC forms (attached). |
| L NRC Form 366 contains an abstract that provides a brief description of the evaluated condition. For a complete description of the evaluated condition, refer to the text of the report provided on Form 366A. | | L NRC Form 366 contains an abstract that provides a brief description of the evaluated condition. For a complete description of the evaluated condition, refer to the text of the report provided on Form 366A. |
| l This condition did not adversely affect the health and safety of the public. For additional information L regarding this LER contact Adam Miller of the TMI Nuclear Safety & Licensing Department at (717) 948-8128. | | l This condition did not adversely affect the health and safety of the public. For additional information L |
| Sincerely, /- | | regarding this LER contact Adam Miller of the TMI Nuclear Safety & Licensing Department at (717) 948-8128. |
| | Sincerely, |
| | /- |
| | %1Lis N ks |
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| I | | I |
| %1Lis N ks '
| | } |
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| | mes W. Langenba Vice President and Director, TMI AWM |
| mes W. Langenba Vice President and Director, TMI - | | / ~ |
| AWM / ~
| | . cc: |
| . cc: TMI Senior Resident Inspector j Administrator, Region I ' d TMI-2 Senior Project Manager File 98105 ,
| | TMI Senior Resident Inspector j |
| 1 9807100326 990702 PDR ADOCK 05000320 S ,_ .PDR
| | Administrator, Region I ' |
| | d TMI-2 Senior Project Manager File 98105 1 |
| | 9807100326 990702 PDR ADOCK 05000320 S |
| | .PDR |
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Similar Documents at Crane |
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LER-1998-001, Forwards LER 98-001-00 Re Condition Which Was Evaluated & Determined to Be Reportable on 980615.NRC Form 366 Contains Abstract,Providing Brief Description of Evaluated Condition |
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| 3201998001R00 - NRC Website |
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l GPU Nuclear,Inc.
(
Route 441 South l
NUCLEAR P**' **'i c
Middletown, PA 17057-0480 Tel 717-944-7621 July 02,1998 1920-98-20355 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Dear Sir:
Subject:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Possescion Only License No. DPR-73 Docket No. 50-320 LER 98-001-00, " Flood Barriers Breached Between the Turbine Building and the Control Building Area Due to Inadequate Fieldwork Documents" This letter transmits Licensee Event Report (LER) number 98-001-00 cencerning :. condition which
. was evaluated and determined to be reportable on June 15,1998.
This LER is being submitted pursuant to 10 CFR 50.73, using the required NRC forms (attached).
L NRC Form 366 contains an abstract that provides a brief description of the evaluated condition. For a complete description of the evaluated condition, refer to the text of the report provided on Form 366A.
l This condition did not adversely affect the health and safety of the public. For additional information L
regarding this LER contact Adam Miller of the TMI Nuclear Safety & Licensing Department at (717) 948-8128.
Sincerely,
/-
%1Lis N ks
(
I
}
mes W. Langenba Vice President and Director, TMI AWM
/ ~
. cc:
TMI Senior Resident Inspector j
Administrator, Region I '
d TMI-2 Senior Project Manager File 98105 1
9807100326 990702 PDR ADOCK 05000320 S
.PDR
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| 05000320/LER-1998-001, Forwards LER 98-001-00 Re Condition Which Was Evaluated & Determined to Be Reportable on 980615.NRC Form 366 Contains Abstract,Providing Brief Description of Evaluated Condition | Forwards LER 98-001-00 Re Condition Which Was Evaluated & Determined to Be Reportable on 980615.NRC Form 366 Contains Abstract,Providing Brief Description of Evaluated Condition | | | 05000320/LER-1998-001-02, :on 980604,flood Barriers Breached Between Turbine Bldg & Control Bldg Area.Caused by Work Planning Process for Dismantlement Work Failed to Include Adequate Controls.Openings Verified to Be Sealed |
- on 980604,flood Barriers Breached Between Turbine Bldg & Control Bldg Area.Caused by Work Planning Process for Dismantlement Work Failed to Include Adequate Controls.Openings Verified to Be Sealed
| 10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1998-001, :on 980122,failure to Operate & Maintain Flow Instruments within Design Basis Occurred.Caused by Improper Application of Stds for Resolution of Degraded or non- Conforming Conditions.Operators Trained |
- on 980122,failure to Operate & Maintain Flow Instruments within Design Basis Occurred.Caused by Improper Application of Stds for Resolution of Degraded or non- Conforming Conditions.Operators Trained
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000289/LER-1998-002-01, Forwards LER 98-002-01,providing Addl Info Addressing Reason for Event,Extent of Problem Associated W/Missing Operator Aid,Assessment of Safety Consequences of Event & Corrective Actions Taken | Forwards LER 98-002-01,providing Addl Info Addressing Reason for Event,Extent of Problem Associated W/Missing Operator Aid,Assessment of Safety Consequences of Event & Corrective Actions Taken | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000289/LER-1998-003, :on 980218,discovered Installation of Thermo- Lag Fire Barrier on Incorrect Conduit Duct.Caused by Personnel Error.Revised Operating Procedure 1104-45 & Installed One Hour Fire Rated Barrier on Subject Cable Duct |
- on 980218,discovered Installation of Thermo- Lag Fire Barrier on Incorrect Conduit Duct.Caused by Personnel Error.Revised Operating Procedure 1104-45 & Installed One Hour Fire Rated Barrier on Subject Cable Duct
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1998-004, :on 980218,loss of CS Capability Was Noted. Caused by Improper Assembly of RBS Pump Discharge Valve Control Switch Pushbutton.Pushbutton Switch Was Replaced W/New Properly Assembled Pushbutton Switch |
- on 980218,loss of CS Capability Was Noted. Caused by Improper Assembly of RBS Pump Discharge Valve Control Switch Pushbutton.Pushbutton Switch Was Replaced W/New Properly Assembled Pushbutton Switch
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1998-005-01, Forwards LER 98-005-01,re Inoperable Fire Dampers.Revised LER Includes Supplemental Info Addressing Results of Root Cause Evaluation | Forwards LER 98-005-01,re Inoperable Fire Dampers.Revised LER Includes Supplemental Info Addressing Results of Root Cause Evaluation | | | 05000289/LER-1998-005, Forwards LER 98-005-00 Re Inoperable Fire Dampers Determined Reportable on 980416.No New Commitments Made within Ltr | Forwards LER 98-005-00 Re Inoperable Fire Dampers Determined Reportable on 980416.No New Commitments Made within Ltr | | | 05000289/LER-1998-006-01, :on 980617,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement,Was Identified.Caused by Personnel Error.Hourly Fire Watch Initiated |
- on 980617,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement,Was Identified.Caused by Personnel Error.Hourly Fire Watch Initiated
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1998-006, Forwards LER 98-006-00,re Thermo-Lag Fire Barrier That Was Found Installed Outside Approved Joint Design Arrangement | Forwards LER 98-006-00,re Thermo-Lag Fire Barrier That Was Found Installed Outside Approved Joint Design Arrangement | | | 05000289/LER-1998-007, Forwards LER 98-007-00, Inoperable Intake Screen & Pump House Floor Drain Check Valves Due to Lack of Preventive Maint & Periodic Insps, Per 10CFR50.73.Rept Was Evaluated & Determined Reportable on 980720.W/o Encl | Forwards LER 98-007-00, Inoperable Intake Screen & Pump House Floor Drain Check Valves Due to Lack of Preventive Maint & Periodic Insps, Per 10CFR50.73.Rept Was Evaluated & Determined Reportable on 980720.W/o Encl | | | 05000289/LER-1998-008-01, :on 980818,RM RM-A-8G-High Was Noted Inoperable for More than 7 Days.Caused by Weaknesses in I&C Work Practices.Revised Data Collection Portion of Surveillance Procedures |
- on 980818,RM RM-A-8G-High Was Noted Inoperable for More than 7 Days.Caused by Weaknesses in I&C Work Practices.Revised Data Collection Portion of Surveillance Procedures
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1998-008, Forwards LER 98-008-00,re Radiation Monitor RM-A8G-High Which Was Inoperable for More than 7 Days Due to Less than Adequate Performance of Calibr Surveillance | Forwards LER 98-008-00,re Radiation Monitor RM-A8G-High Which Was Inoperable for More than 7 Days Due to Less than Adequate Performance of Calibr Surveillance | | | 05000289/LER-1998-009, Forwards LER 98-009-00 Re Potential Loss of HPI During Postulated LOCA with Most Limiting Single Failure.Caused by Misapplication of Design Inputs When Operating Procedures Were Changed Prior to Startup for Current Operating Cy | Forwards LER 98-009-00 Re Potential Loss of HPI During Postulated LOCA with Most Limiting Single Failure.Caused by Misapplication of Design Inputs When Operating Procedures Were Changed Prior to Startup for Current Operating Cycle | | | 05000289/LER-1998-009-01, :on 980820,discovered Potential Loss of HPI During Postulated Loca.Caused by Misapplication or Interpretation of Design Inputs.Revised OL Was Implemented & Mut Pressure & Level Limits Analysis Revised |
- on 980820,discovered Potential Loss of HPI During Postulated Loca.Caused by Misapplication or Interpretation of Design Inputs.Revised OL Was Implemented & Mut Pressure & Level Limits Analysis Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1998-010-01, :on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued |
- on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1998-010, Forwards LER 98-010-00 Re Potential Violation of Design Criteria During Single Auxiliary Transformer Operation Reported on 980825.Second & Associated Issue Was Identified & Reported on 980916,as Suppl Info IAW 10CFR50.72(c) | Forwards LER 98-010-00 Re Potential Violation of Design Criteria During Single Auxiliary Transformer Operation Reported on 980825.Second & Associated Issue Was Identified & Reported on 980916,as Suppl Info IAW 10CFR50.72(c) | | | 05000289/LER-1998-011-01, Forwards LER 98-011-01,which Updates & Replaces Info Re Thermo-Lag Fire Barriers Found Installed Outside Approved Joint Arrangement.Rept Was Determined Reportable on 980825 & Reported Via LER 98-011-00 on 980923 | Forwards LER 98-011-01,which Updates & Replaces Info Re Thermo-Lag Fire Barriers Found Installed Outside Approved Joint Arrangement.Rept Was Determined Reportable on 980825 & Reported Via LER 98-011-00 on 980923 | | | 05000289/LER-1998-012, :on 980828,discovered That Control Bldg Ventilation Damper AH-D-270 Had Been Opened Approx 50% for as Long as 54 Days.Caused by Lack of Controls for Subject Damper.Immediately Closed & Tagged Damper AH-D-270 |
- on 980828,discovered That Control Bldg Ventilation Damper AH-D-270 Had Been Opened Approx 50% for as Long as 54 Days.Caused by Lack of Controls for Subject Damper.Immediately Closed & Tagged Damper AH-D-270
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1998-013-01, Forwards LER 98-013-01 Re Failure to Perform Fire Protection Program Surveillances at Required Frequency.Completed Corrective Actions Described in Section Viii of Attached Rept Constitute Commitments Made to Reduce Occurrenc | Forwards LER 98-013-01 Re Failure to Perform Fire Protection Program Surveillances at Required Frequency.Completed Corrective Actions Described in Section Viii of Attached Rept Constitute Commitments Made to Reduce Occurrence | | | 05000289/LER-1998-014-01, :on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With |
- on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With
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