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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARLG-83-363, Significant Interim Deficiency Rept Re Gulf & Western Fitting/Matl Certification Irregularities.Initially Reported on 830311.Documentation Reviewed & Addl Tests Performed.Matl Specs Met1983-04-15015 April 1983
Significant Interim Deficiency Rept Re Gulf & Western Fitting/Matl Certification Irregularities.Initially Reported on 830311.Documentation Reviewed & Addl Tests Performed.Matl Specs Met
ML20031D3261981-10-0101 October 1981
Final Deficiency Rept 81/01-5PS-491 Re Apparent Breakdowns in Mfg Cleaning & Insp Processes on Shutdown Heat Exchangers,Initially Reported 801217.Repairs Completed.Insp Results Indicated That Deficiencies Have Been Corrected
ML20009F6741981-07-14014 July 1981
Interim Deficiency Rept Re NSSS Shutdown Heat Exchanges, Initially Reported on 801217.Recladding of Tube Sheet Required for Unit 1A.Clad Surfaces Acceptable for Unit 1B. Next Rept Will Be Submitted by 811001
ML20009C5441981-07-14014 July 1981
Deficiency Rept on Shutdown Heat Exchangers,Initially Reported on 801217.Unit 1A & 1B Exchangers Removed from Reactor Bldg & Returned to Supplier for Exam & Repair.Exam Results Provided.Next Rept Will Be Submitted by 811001
ML19341A4281981-01-15015 January 1981
Interim Deficiency Rept,Originally Reported on 801217,re Breakdowns in Mfg,Cleaning & Insp Processes on Shutdown Heat Exchangers.Caused by Contamination of Tube Side Matl Surfaces.Exchangers Returned to Supplier for Exam & Repair
ML19323J3271980-06-0606 June 1980
Final Part 21 Rept Re Mixed Heat of Steel Supplied by Us Steel from Which 4-inch Elbows & 2-inch Tees Were Mfg to A234WPB Requirement.Investigations Conducted & Closed at 46 Listed Facilities
ML19259C1951979-05-11011 May 1979
Final Rept 79/01-5PS-491/492/493:weld Fittings W/Lot Number W6719 Contained Erroneously Identified High Carbon Steel Matl That Could Crack When Being Welded.All Matl Returned to Vendor on 790412
1983-04-15
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20095E4441983-12-31031 December 1983
1983 Annual Rept
LG-83-363, Significant Interim Deficiency Rept Re Gulf & Western Fitting/Matl Certification Irregularities.Initially Reported on 830311.Documentation Reviewed & Addl Tests Performed.Matl Specs Met1983-04-15015 April 1983
Significant Interim Deficiency Rept Re Gulf & Western Fitting/Matl Certification Irregularities.Initially Reported on 830311.Documentation Reviewed & Addl Tests Performed.Matl Specs Met
ML20063E6711982-02-15015 February 1982
Annual Financial Rept 1981
ML20031D3261981-10-0101 October 1981
Final Deficiency Rept 81/01-5PS-491 Re Apparent Breakdowns in Mfg Cleaning & Insp Processes on Shutdown Heat Exchangers,Initially Reported 801217.Repairs Completed.Insp Results Indicated That Deficiencies Have Been Corrected
ML20009F6741981-07-14014 July 1981
Interim Deficiency Rept Re NSSS Shutdown Heat Exchanges, Initially Reported on 801217.Recladding of Tube Sheet Required for Unit 1A.Clad Surfaces Acceptable for Unit 1B. Next Rept Will Be Submitted by 811001
ML20009C5441981-07-14014 July 1981
Deficiency Rept on Shutdown Heat Exchangers,Initially Reported on 801217.Unit 1A & 1B Exchangers Removed from Reactor Bldg & Returned to Supplier for Exam & Repair.Exam Results Provided.Next Rept Will Be Submitted by 811001
ML19341A4281981-01-15015 January 1981
Interim Deficiency Rept,Originally Reported on 801217,re Breakdowns in Mfg,Cleaning & Insp Processes on Shutdown Heat Exchangers.Caused by Contamination of Tube Side Matl Surfaces.Exchangers Returned to Supplier for Exam & Repair
ML19323J3271980-06-0606 June 1980
Final Part 21 Rept Re Mixed Heat of Steel Supplied by Us Steel from Which 4-inch Elbows & 2-inch Tees Were Mfg to A234WPB Requirement.Investigations Conducted & Closed at 46 Listed Facilities
ML19323A1621980-03-26026 March 1980
TMI-Plus One:Toward a Safer Nuclear Power Program
ML19259C1951979-05-11011 May 1979
Final Rept 79/01-5PS-491/492/493:weld Fittings W/Lot Number W6719 Contained Erroneously Identified High Carbon Steel Matl That Could Crack When Being Welded.All Matl Returned to Vendor on 790412
ML19316A4671978-02-0909 February 1978
Annual Financial Rept 1977
ML19242D9141977-03-31031 March 1977
SER Re Const of Facilities
ML19312C2401977-03-22022 March 1977
Annual Financial Rept 1976
ML19308A7911976-04-26026 April 1976
Annual Financial Rept 1975
ML19308A7881975-04-0202 April 1975
Annual Financial Rept 1974
1983-04-15
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Text
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i DUKE POWER COMPANY
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GENERAL OFFICES
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422 SOUTH CHURCH STREE!
CHARLO'l'I'E. N. C. 28242
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l s'anuary 15, d81 Mr. J. P. O'Reilly, Director U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re:
Cherokee Nuclear Station, Unit 1 Docket No. 50-491 IE 81/01-5PS-491 NSSS-Shutdown Heat Exchanger Duke Files: CK-1412.ll-1
Dear Mr. O'Reilly:
Attached is Duke's interim report on the referenced 10CFR50.55(e) reportable item.
Another report will be submitted by July 15, 1981 Initial notification was made by telephone to Mr. Rausch of your office on December 17, 1980.-
Very truly yours, f
Li C. Dail, Vice-President Design Engineering Department JEB/pam Attachment cc: Director of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 gen
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O DUKE POWER C0.
CHEROKEE NUCLEAR STATION Report Number:
IE 81/01-5PS-491 Report Date: January 15, 1981 Facility: Cherokee Nuclear Station - Unit #1 Identification of Deficiency:
Apparent breakdowns in manufacturing, cleaning, and inspection processes on Shutdown Heat Exchangers (SDHX's).
Description of Deficiency:
On December 17,196., Mr. R. E. Miller and Mr. W. H. Bradley informed Mr. John Rausch, NRC of potential deficiencies in the Shutdown Heat Exchangers, supplied by Combustion Engineering as part of the NSSS contract, on the following basis:
1.
Due to problems encountered on the WPPSS Unit #3 SDHX, and since the Duke SDHX's were manufactured by the' same vendor (Ametek), CE advised Duke that these heat exchangers were suspect.
2.
The Duke Unit #1 SDHX's were preliminarily inspected at the site, and were found to have problems with the stainless steel cladding and contamination of tube side material surfaces.
Analysis of Safety Implications:
The SDHX's provide a safety related function in both the containment spray and shutdown cooling modes of operation of the Containment Spray System.
The containment spray mode is designed to remove heat from the containment atmosphere in the event of a LOCA or MSLB inside the containment. The SDHX cools the containment s ray water as it recirculates from the containment recirculation sump to the spray nozzles.
Loss of one SDHX would delete redundancy in the containment spray mode, while the simultaneous loss of both SDHX's could compromise this mode of heat removal.
In the shutdown cooling mode the SDHX's remove heat during both cooldown and shutdown. During cooldown they remove core decay heat, Reactor Coolant System sensible heat, and safeguards pump heat; during shutdown they remove decay heat, containment spray pump heat, and low pressure safety injection pump heat.
Loss of one SDHX in the shutdown cooling mode would delete redundancy and increase the normal cooldown time for plant shutdown, whi?e the simultaneous loss of both SDHX's could compromise this mode of heat removal.
Corrective Actions:
Duke will remove the Unit l A and IB SDHX's from the Reactor Building, and return them to the original supplier for examination and repair.
Specific corrective actions will be determined over the next 6-12 months. Similar problems will be precluded on Cherokee, Unit 2 and subsequent units not yet under construction.
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