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LER-1997-006, Re Unqualified Cable Terminations.Ler 97-006-00 Retracted |
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| 2891997006R02 - NRC Website |
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GPU Nucleer. Inc.
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Route 441 Soutti NUCLEAR
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Middletown. PA 17057 0480 Tel717 944 7671 6710-97-2493 November 26, 1997 i
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 i
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Gentlemen:
Subject: Three hiite Island Nuclear Station, Unit I (Thil-l)
Operating License No. DPR-50 Docket No. 50-289 i
Retraction of LER 97-006-00 l
l The purpose of this letter is to retract Licensee Event Report (LER) 97-006-00 submitted by GPU Nuclear on hiay 23,1997.
The LER was submitted based on the apparent failure to satisfy Thil-1 Technical Specification 3.3.1 condition for reactor criticality. This specification requires that two Reactor Building Spray pumps and their associated spray nozzle headers, and two Reactor Building Air Recirculation Cooling fans and associated cooling units (one in each train) be operable. A motor fault at a connection to Reactor Building Air Recirculation Cooling fan, AH E-1 A, initiated a corrective maintenance action. A subsequent review identified that the electrical power termination configuration at the fan motor did not conform with established environmental qualification requirements. An evaluation of the terminations at the. EE-1B and 1C fan motors found a similar inadequate environmental qualification (EQ) configuration to exist and the All E-1B and 1C fans were declared inoperable. On April 25,1997, following the inoperability declaration, repairs consistent with the application described by test documentation supporting another utility's environmentally qualifir.1 splice were made to AH E-1B and IC, the motors were returned to sersice.
I GPU Nuclear identified the root cause of the installation of the unqualified cable terminations and completed numerous corrective actions to prevent recurrence of an event of a similar nature.
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6710 97 2493 Page 2 of 2 Those actions included:
Review of engineering and administrative procedures to verify that configuration and material changes for EQ equipment are appropriately reviewed and documented; Review of procedures to assure timely reporting, documentation and resolution of EQ issues; l
a Trainmg provided to Engineering groups on engineering and admiistrative procedure
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requirements and GPU Nuclear's expectations, regarding timeliness of operability i
determinations; Review of planned 12R outage work on EQ components and performance of an Engineering
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walk down of selected components to assure that the configuration is consistent with EQ requirements; and, l
Inspection of components which were identified as candidates for miscommunication of
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installation instmetions by the end of the 12R outage.
l Concurrent with the corrective actions, GPU Nuclear contracted an independent test facility to test the operability of the cable termination configuration existing at All E-l A, B & C from 1986 to 1997. The test was performed to verify the cable terminations ability to operate (perform their Class IE safety-related function) under all sersice conditions, including those during and after an accident. The tests performed on September 26 and 27,1997 found that the as-installed 1986 Reactor Building Air Recirculation Cooling fan cable termination configuration would withstand normal operating and ei.vironmerital accident conditions.
Based on the test results, the Reactor Building Air Recirculation Cooling fans were determined to be operable with the cable termination as originally configured, lience, there was no violation of the Thil-1 Technical Specifications. Although an EQ program deficiency was identified and subsequently corrected, there is no longer suflicient substance to support the LER submitted.
LER 97-006-00 is therefore hereby retracted.
Sincerely, p
W ct.
James W. Langenbach Vice President and Director, TM1 WGli cc: Administrator, Region l-liubert J. Miller TMI-l Senior Project Manager, Timothy G. Colburn TMl Senior Resident Inspector-Wayne L. Schmidt
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| 05000289/LER-1997-001, Forwards Corrected Copy of LER 97-001-00 Re Condition Found During Review of GL 96-06 | Forwards Corrected Copy of LER 97-001-00 Re Condition Found During Review of GL 96-06 | | | 05000289/LER-1997-001-02, :on 970117,potential Overpressurization of Piping Between Closed Reactor Building Containment Isolation Valves Occurred Due to Inadequate Design Code Guidance. Results of Review Will Be Documented.Pages 2 & 3 Corrected |
- on 970117,potential Overpressurization of Piping Between Closed Reactor Building Containment Isolation Valves Occurred Due to Inadequate Design Code Guidance. Results of Review Will Be Documented.Pages 2 & 3 Corrected
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1997-001-01, :on 970117,potential Overpressurization of Piping Between Closed Reactor Building Isolation Valves Occurred Due to Inadequate Design Code Guidance.Results of This Review Will Be Documented |
- on 970117,potential Overpressurization of Piping Between Closed Reactor Building Isolation Valves Occurred Due to Inadequate Design Code Guidance.Results of This Review Will Be Documented
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1997-002, :on 970129,potential Inability of Startup Feedwater Block Valves to Fully Close Following Main Steam Line Break Occurred Due to MOV Program Weakness.Increased Torque Switch Settings on Valve Operators |
- on 970129,potential Inability of Startup Feedwater Block Valves to Fully Close Following Main Steam Line Break Occurred Due to MOV Program Weakness.Increased Torque Switch Settings on Valve Operators
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1997-003-01, Forwards LER 97-003-01 Re Potential Overpressurization of Makeup Pump Suction Piping,Due to Inadequate Test & Operating Procedures | Forwards LER 97-003-01 Re Potential Overpressurization of Makeup Pump Suction Piping,Due to Inadequate Test & Operating Procedures | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000289/LER-1997-004, :on 970228,declared Auxiliary & Fuel Handling Bldg Ventilation Sys Inoperable.Cause Related to Wording in TS Bases & Fsar.All Sys Maint,Testing & Design Mods Performed |
- on 970228,declared Auxiliary & Fuel Handling Bldg Ventilation Sys Inoperable.Cause Related to Wording in TS Bases & Fsar.All Sys Maint,Testing & Design Mods Performed
| 10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1997-005-01, :on 970410,declared motor-operated Reactor Bldg Purge Valves Inoperable Due to Inadequate Closing Torque. Caused by Deficient Design Analysis.Will Perform Evaluation of Valve Specific Seating Torque Test Data |
- on 970410,declared motor-operated Reactor Bldg Purge Valves Inoperable Due to Inadequate Closing Torque. Caused by Deficient Design Analysis.Will Perform Evaluation of Valve Specific Seating Torque Test Data
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1997-005, Has Been Cancelled | Has Been Cancelled | | | 05000289/LER-1997-006-01, :on 970424,reactor Bldg Fan Motors Unqualified Cable Termination Occurred Due to Incorrect Engineering Guidance.Caused by Personnel Error.Qualifiable Repair of AH-E-1A Fan Motor Termination Was Installed on 970323 |
- on 970424,reactor Bldg Fan Motors Unqualified Cable Termination Occurred Due to Incorrect Engineering Guidance.Caused by Personnel Error.Qualifiable Repair of AH-E-1A Fan Motor Termination Was Installed on 970323
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1997-006, Forwards LER 97-006-00,resulting from Violation of TS 3.3 & Declaring Reactor Bldg fans,AH-E-1B & C,Inoperable on 970424 | Forwards LER 97-006-00,resulting from Violation of TS 3.3 & Declaring Reactor Bldg fans,AH-E-1B & C,Inoperable on 970424 | | | 05000289/LER-1997-006-02, Re Unqualified Cable Terminations.Ler 97-006-00 Retracted | Re Unqualified Cable Terminations.Ler 97-006-00 Retracted | | | 05000289/LER-1997-007, :on 970621,generator Output Breaker Failed Resulting in Loss of Offsite Power & Rt.Caused by Failure of Generator Breaker GB-102.Both Failed Breakers Were Replaced |
- on 970621,generator Output Breaker Failed Resulting in Loss of Offsite Power & Rt.Caused by Failure of Generator Breaker GB-102.Both Failed Breakers Were Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1997-008, :on 970621,power to Control Rod Drive Mechanisms Was Lost & Reactor Tripped.Caused by Long Trip Insertion Times at Tmi.Rods Were Trip Tested Per Surveillance Procedure 1303.11.1 |
- on 970621,power to Control Rod Drive Mechanisms Was Lost & Reactor Tripped.Caused by Long Trip Insertion Times at Tmi.Rods Were Trip Tested Per Surveillance Procedure 1303.11.1
| 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(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1997-009-01, :on 970725,engineering Analysis of Loss of a Train DC Power W/Loss of Offsite Power & LOCA Was Determined.Caused by Plant Designers Error.Trained Operators on Methodology to Regain Control of Es Equipment |
- on 970725,engineering Analysis of Loss of a Train DC Power W/Loss of Offsite Power & LOCA Was Determined.Caused by Plant Designers Error.Trained Operators on Methodology to Regain Control of Es Equipment
| 10 CFR 50.73(a)(2)
10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1997-009, Forwards LER 97-009-00,re Condition Which Was Evaluated & Determined to Be Reportable on 970725.Condition Was Identified as Result of Review of Crystal River 3 LER for Applicability at TMI-1 | Forwards LER 97-009-00,re Condition Which Was Evaluated & Determined to Be Reportable on 970725.Condition Was Identified as Result of Review of Crystal River 3 LER for Applicability at TMI-1 | | | 05000289/LER-1997-010, Forwards LER 97-010-00,concerning Inoperable PORV Resulting from Violation of TS 4.2.2,in that,post-maintenance Test Was Not Performed on PORV Following Replacement During 11R Refueling | Forwards LER 97-010-00,concerning Inoperable PORV Resulting from Violation of TS 4.2.2,in that,post-maintenance Test Was Not Performed on PORV Following Replacement During 11R Refueling | | | 05000289/LER-1997-010-01, :on 971012,PORV Inoperability Was Determined. Caused by mis-wiring & Failure to Perform post-maintenance Test Following Replacement During 11R Refueling Outage.Porv Replaced During 12R Refueling Outage Was Wired Correctly |
- on 971012,PORV Inoperability Was Determined. Caused by mis-wiring & Failure to Perform post-maintenance Test Following Replacement During 11R Refueling Outage.Porv Replaced During 12R Refueling Outage Was Wired Correctly
| 10 CFR 50.73(a)(2)(i) |
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