05000413/LER-1999-009-01, Forwards LER 99-009-01,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits. Commitments Are Contained in Planned Corrective Actions Section of Attached Rept
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05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments
05000414/LER-1999-002, Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 990708
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05000414/LER-1999-003, Forwards LER 99-003-00,re Unplanned Actuation of Esfa Sys. Supplemental LER Is Expected to Be Submitted by 990831
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05000414/LER-1999-004, Forwards LER 99-004-00,re Containment Isolation Valve 2NM-221A Returned to Service Without Testing.Revised Rept Will Be Submitted to Include Addl Details When Rept Is Finalized
05000414/LER-1999-001-01, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Perfor
05000413/LER-1999-010-01, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units
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05000413/LER-1999-009-01, Forwards LER 99-009-01,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits. Commitments Are Contained in Planned Corrective Actions Section of Attached Rept
05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments
NLS9000259, Responds to Violations Noted in Insp Repts 50-369/90-09 & 50-370/90-09.Corrective actions:in-house Training Will Be Provided on Correct Method for Determining Proper Response to Problem Investigation Processes
llat R hher Dde her Company i)ce hesident p>0 tua33198 Nudear 1% duction Charlotte. N C 2"42 (704)373,4531 OliKL POWER August 17, 1990 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555
Subject:
Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-413 and 50-414 McGuire Nuclear Station Docket Nos. 50-369 and 30-370 Main Steam Line Breaks In Ice Condenser Plants Gentlemen:
By letter dated May 11, 1989, the NRC Staff requested that Duke Power Company review and comment on Argonne National Laboratory's (ANL) confirmatory analysis which was performed to validate conclusions made relative to Main Steam Line Breaks (MSLBs) inside an Ice Condenser Containment. Of specific concern were the superheated temperatures the ANL analysis predicted in the vicinity of the break locations which exceeded the Environmental Qualification (EQ) limit of 327'F.
My letter dated July 17, 1989 transmitted Duke Power Company's comments which concluded that local temperatures near the break could exceed the EQ limit, but that there was no equipment required for MSLB mitigation close enough to the break locations to be affected. Additionally, Duke provided a technical justification as to why the COBRA-NC temperature predictions are more accurate than those predicted by the COMMIX code.
Attached is a supplement to my July 17, 1989 letter, which provides additional information to support Duke Power's position on this issue.
Mr. Stewart'D. Ebneter Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, Georgia 30323 Dr. K. N. Jabbour Office of Nuclear Reactor Regulation U. S.. Nuclear Regulatory Commission