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MONTHYEARML20005B2251981-07-0101 July 1981
Responds to Generic Ltr 81-04 Re Commitments for Implementation of NUREG-0313.Inservice Insp Exams Performed on Stainless Steel Piping Sys Revealed No Evidence of Intergranular Stress Corrosion Cracking
Project stage: Other
IR 05000312/19820161982-05-0505 May 1982
IE Insp Rept 50-312/82-16 on 820401-0502.No Noncompliance Noted.Major Areas Inspected:Operational Safety verification,long-term Shutdown Activities,Maint & Surveillance Observations & Followup on Regional Requests
Project stage: Request
05000368/LER-1982-020-03, /03L-0:on 820529,during Power Escalation,Battery Bank 2D01 Voltage Dropped to 121-volts Dc.Caused by Primary Voltage Supply to Inverters 2Y-11,2Y-13 & 2Y-25 Switching to Battery Bank 2D011982-06-25025 June 1982
/03L-0:on 820529,during Power Escalation,Battery Bank 2D01 Voltage Dropped to 121-volts Dc.Caused by Primary Voltage Supply to Inverters 2Y-11,2Y-13 & 2Y-25 Switching to Battery Bank 2D01
Project stage: Other
ML20027B5391982-09-13013 September 1982
Forwards Requested Info Re Auxiliary Feedwater Stabilized Internal Header.Includes B&W Info Re Commitment to Prepare Design Rept for Modified Steam Generator & Auxiliary Feedwater Piping Sys
Project stage: Other
ML20067C9501982-12-0202 December 1982
Responds to NRC 821108 Request for Addl Info Re Response to Generic Ltr 81-04.Selection of Welds in Loop of Large Bore Reactor Recirculation Piping Will Be Examined During 1983 Refueling Outage
Project stage: Request
05000298/LER-1983-011-01, /01T-0:on 830710,welds CSA-BJ-5 & 6 Found Leaking During Grinding of Weld Crowns.Caused by Intergranular Stress Corrosion Cracking.Welds to Be Repaired by Weld Overlay Methods.Piping Will Be Replaced1983-07-20020 July 1983
/01T-0:on 830710,welds CSA-BJ-5 & 6 Found Leaking During Grinding of Weld Crowns.Caused by Intergranular Stress Corrosion Cracking.Welds to Be Repaired by Weld Overlay Methods.Piping Will Be Replaced
Project stage: Other
ML20024D9811983-07-28028 July 1983
Advises That Responsibility for Evaluating Proposed Actions Re IE Bulletin 83-02 Concerning Recirculation Sys Pipe Cracks Transferred to Div of Licensing
Project stage: Other
ML20093M7941983-07-31031 July 1983
Technical Evaluation of Integrity of Cooper Nuclear Station Reactor Coolant Boundary Piping Sys
Project stage: Other
A830019, Forwards Info Re Intergranular Stress Corrosion Cracking Observed in Core Spray & Reactor Water Cleanup Sys,Per 830822 Request.Weld Overlay Repairs Meet Safety Margins of App X to Section IX of ASME Code1983-08-23023 August 1983
Forwards Info Re Intergranular Stress Corrosion Cracking Observed in Core Spray & Reactor Water Cleanup Sys,Per 830822 Request.Weld Overlay Repairs Meet Safety Margins of App X to Section IX of ASME Code
Project stage: Other
ML20080D8071983-08-25025 August 1983
Forwards Revised Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements of Coolant Leakage, During Cycle 9 Operation,Per 830824 Request
Project stage: Other
ML20080D8231983-08-25025 August 1983
Revised Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements of Coolant Leakage During Cycle 9 Operation
Project stage: Other
NLS8400159, Responds to 840419 Generic Ltr 84-11 Re Insps for IGSCC & Interim Leakage Detection.Requirements Imposed by 830901 Confirmatory Order Meet Intent of Leak Detection & Leakage Limits.Lists Components to Be Replaced1984-06-0404 June 1984
Responds to 840419 Generic Ltr 84-11 Re Insps for IGSCC & Interim Leakage Detection.Requirements Imposed by 830901 Confirmatory Order Meet Intent of Leak Detection & Leakage Limits.Lists Components to Be Replaced
Project stage: Other
NLS8400289, Forwards Weld Repair Criteria Development Summary Re Inconel Nozzle Buttering.Use of Repair Method May Be Required as Early as 841220 at Site1984-12-13013 December 1984
Forwards Weld Repair Criteria Development Summary Re Inconel Nozzle Buttering.Use of Repair Method May Be Required as Early as 841220 at Site
Project stage: Other
ML20117A2321985-04-30030 April 1985
Responds to Item 2 of Generic Ltr 84-11 by Confirming Replacement of All Stainless Steel Piping Welds Susceptible to Igscc.Inconel Nozzle Buttering Repair Procedure Utilized on One Nozzle.Repair Outline & Drawing Encl
Project stage: Other
ML20133G2751985-07-31031 July 1985
Informs That Util Submittals Re 830901 Order & Generic Ltr 84-11 Concerning Recirculation Piping Replacement Program Acceptable.No Augmented Insps Required Prior to Cycle 10 Startup
Project stage: Other
ML20236K8261987-08-0404 August 1987
Notice of Violation from Insp on 870720-24.Violation Noted: ESF Isolation of RWCU That Occurred on 870505 Not Reported as LER
Project stage: Other
1983-07-31
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GENERAL OFFICE Nebraska Public Power District
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LQA8300201 August 25, 1983 Director of Nuclear Reactor Regulation Attention:
Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 Subj ect : Recirculation System IGSCC Repair Commitments
[
Cooper Nuclear Station NRC Docket No. 50-298, DPR-46
Dear Mr. Vassallo:
On August 24, 1983 our NRC Project Manager requested a commitment from Nebraska Public Power District relating to coolant leakage during cycle 9 operation. Attached in the form of a revised page to our Technical Specifications are the additional provisions by which Cooper
- h 1aar % tinri will he operated during cycle 9.
The District will submit plans for inspection, corrective actions and/or modifications, including replacement of the recirculation and other reactor cooling pressure boundary piping systems during the next refueling outage at least three months before the start of the next refueling outage.
Sincerely, M
M. Pilant Technical Staff Manager Nuclear Power Group JDW:cmk Attachment 4
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