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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24302A2772024-10-28028 October 2024 57243-EN 57243_5 - Rssc Dba Marmon - Update 20241030 ML17223A1982017-07-21021 July 2017 Part 21 Notification - Eaton/Cutler Hammer A200 Series Starter PLA-7613, Interim Report of a Deviation, Units 1 & 2 - (PLA-7613)2017-06-0909 June 2017 Interim Report of a Deviation, Units 1 & 2 - (PLA-7613) ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML16313A0622016-10-18018 October 2016 C&D Technologies, Inc. - 10 CFR Part 21 Evaluation Regarding Terminal Welding Failure in 3DCU-9 Batteries ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML12347A3082012-12-12012 December 2012 Part 21 60-Day Interim Report Notification: Error in Main Steam Line High Flow Calculational Methodology ML12319A0122012-09-27027 September 2012 Error in Main Steam Line High Flow Calculational Methodology ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld ML1127000672011-09-26026 September 2011 GE-Hitachi Part 21 Reportable Condition Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML11115A0392011-04-14014 April 2011 Notice of Deviation Pursuant to 10 CFR 21, NPKC-7-21A(N) Splice Kit with Possible Compromised Jacket Seal ML1025202192010-09-0303 September 2010 Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1018907392010-07-0101 July 2010 Part 21 Report Concerning Failure of Turbine Overspeed Reset Control Valve Diaphragm ML1015305642010-05-28028 May 2010 Part 21 Notification from C & D Technologies, Inc., Post Corrosion on Dcu Batteries ML1009604492010-04-0202 April 2010 Part 21 Report by Tyco Valves and Controls, LP Possible Failure of Solenoid Valves with Dual Function Main Steam Safety Valves ML0934301402009-12-0202 December 2009 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 1OCFR21-0098, Rev. 0, Amot Thermostatic Valve Element, P/N: 9760X ML0232901622002-11-18018 November 2002 Final Report, Stability Option III: Possible Successive Confirmation Count Resets - Not Reportable ML18024A0581978-09-18018 September 1978 Letter Attaching a Final Report of a Deficiency in Carriage Bolt Fasteners Used on 480 Volt Motor Control Center Bus Splices ML18024A1011978-07-19019 July 1978 Letter Attaching a Report of Defects Discovered During Qualification and Manufacturing of Control Room Systems ML18024A0661978-07-14014 July 1978 Letter Referring to the April 17, 1978 Letter and Regarding an Update of Interim Report of Reportable Deficiency Regarding Potential Transformers on 4.16K Switchgear ML18024A0681978-07-0505 July 1978 Letter Referring to the April 26, 1978 Letter and Advising the Commission That a Definitive Report Will Be Submitted by September 29, 1978 ML18024A0771978-06-23023 June 1978 Letter Referring to the June 22, 1977 Letter and Relating to the Definitive Report, Prepared by Bechtel Power Corp., of a Reportable Deficiency Regarding Unsatisfactory Field Welding and Inspection of Shear Suds ML18024A0691978-05-31031 May 1978 Letter Referring to the December 1, 1977 Letter Providing an Interim Report of a Deficiency in Physical Separation of Electrical Circuits and Advising the Commission That the Definitive Report Will Be Submitted by September ML18024A0711978-04-26026 April 1978 Letter Attaching Bechtel Engineering'S Interim Report on Spot Welding of Struts for SSES Units 1 and 2 and Advising the Commission That the Definitive Report Will Be Submitted by July 31, 1978 ML18025A4791976-11-0505 November 1976 Interim Report of Reportable Deficiency Defect in RPV Susquehanna Unit 2 Bottom Head Side Plate ML18025A4901975-08-29029 August 1975 Letter Regarding the Definitive Report of Deficiencies in Box Column Supports Which Supplements PLA-74 ML18025A4921975-04-0404 April 1975 Letter Attaching an Interim Report on Potential Deficiency Which Was Discussed with Mr. Heishman on March 6, 1975 2024-10-28
[Table view] Category:Deficiency Report (per 10CFR50.55e and Part 21)
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[Table view] |
Text
og f> +('OS REGULATORY INFORMATION DISTRIBUTION SYSTEM (RI DS )
DISTRIBUTION FOR INCOMING MATERIAL 50-387/388 REC'RIER B H ORG: CURTIS N W DOCDATE: 04/26/78 NRC PA PWR 5 LIGHT DATE RCVD: 05/Oi/78 DOCTYPE: LETTER . NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING CQNSTRUCTION DEFICIENCY REPT CONCERNING SPOT WELDING OF STRUTS FOR SUBJECT FACILITY> CONTAINING BECHTEL ENGINEERING"S EVALUATION OF THIS REPT.
PLANT NAME:SUSQUEHANNA UNIT i REVIEWER INITIAL: X JM SUSQUEHANNA UNIT 2 DISTR IBUTER INITIAL:
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS CONSTRUCTION DEFICIENCY REPORT <iOCFR50. 55<E).
(DISTRIBUTION CODE 8004)
FOR ACTION: ASST DIR VASSALLO~~LTR ONLY BR CHIEF PARR+4LTR ONLY P '- f5R MD! ~~+LTR ONLY LIC ASST RUSHBROOK<<LTR ONLY INTERNAL: REG FILE4+W/ENCL NRC PDR++W/ENCL OELDw+LTR ONLY GOSSICK 8( STAFF++LTR ONLY MIPC+<W/ENCL BOYD++LTR ONLY DEYOUNG++W/ENCL HELTEMES~~W/ENCL R. MATTSON+~LTR ONLY KNIGHT+4LTR ONLY ROSS++LTR ONLY TEDESCO++LTR ONLY EISENHUT++LTR ONLY STANDARDS DEV. +>W/ENCL K SEYFR IT/IE++W/ENCL EXTERNAL: LPDRiS WILKES BARREi PA++W/ENCL TIC++W/ENCL I
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ve~sesIs~'va eaIa e aawbn+v~ a eels'aTF'r,' vsryysri ~Aa hiero~~ cfear're+i,+pq TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONE: (215) 821-5151 NORMAN W. CURTIS Vice President-Engineering & Construction 821-5381 April 26, 1978
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NAI g Mr. Boyce H. Grier ~e au 978~
Director, Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 gpgp gyp~
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Dear Mr.'Griers relates to a reportable deficiency, under the provisions of 10CFR5855(e),
f/'his WhiCh WaS,identified tO Mr. A. TOth, NRC-RegiOn I, by Mr. A. R. SabOlr PPGLF during a telephone conversation on 3/27/78. The deficiency involves inadequate spot welding of strut material used in field fabricated supports for safety related electrical raceways, HVAC ducts and instrumentation panels. It is concluded that the inadequate fusion, of the spot welding may result in inadequate strength and, as such, represents a deficiency in construction (fabrication) which may adversely affect the safe operation of the plant under design loading conditions.
Bechtel Engineering's evaluation of the information available at present is contained in the attached "Interim Report on Spot Welding of Struts for Susquehanna Steam Electric Station Units 1 and 2ns We anticipate submittal of the required definitive report of the deficiency by 7/31/78.
Very truly yours, 781220084 N. W. Curtis Vice President-Engineering S Construction Attachment CIM:mcb ado tt. ~ Ail PENNSYLVANIA POWER 8, LIGHT COMPANY t(l
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Mr. B. H.-Grier April 26, 1978 cc: Mr. Ernst Volgenau (15)
Director Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. G. McDonald, Director Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555
ppg >s 78 08g4 gp INTERIM REPORT ON SPOT WELDING OF STRUTS FOR SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 Prepared by:
Checked Approved b Project Engineer z.Q.3cL .~E, BECHTEL POWER, CORPORATION SAN FRANCISCO, CALIFORNIA April 19, 1978 (P-111b)
INTERIM REPORT ON SPOT WELDING OF STRUTS TABLE OF CONTENTS 1.0 PURPOSE
2.0 BACKGROUND
3.0 DESCRIPTION
OF DEFICIENCY 4.0 ANALYSIS OF SAFETY IMPLICATIONS 5.0 CORRECTIVE ACTION 6.0 REMARKS
INTERIM REPORT APR 19'78 085497 ON SPOT WELDING OF STRUT MEMBERS 1.0 PURPOSE The purpose of this interim report is to provide available information pursuant to 10CFR 50.55(e), concerning the deficiencies observed in spot welding of struts.
2.0 BACKGROUND
'Strut members are light gage channels and are produced by cold rolling mild steel strip. The strut members used on Susquehanna Project are manufactured by Unistrut, Wayne,.
Michigan; Power Strut, Division of Van Huffel Tube Corpor-ation, Warren, Ohio and B-Line, Systems Incorporated, Highland, Indiana. The basic member produced is a channel section. These channel sections are sometimes connected to each other in various configurations such as back to back, back t'o side, or side to side by using a welding process'ommercially known as spot welding or resistance welding. This process essentially consists of passing high current through the thicknesses of adjoining members resulting, in metal to metal fusion.
The channel sections and/or built-up sections are used in field fabricated supports for safety related electrical raceways, HVAC ducts and instrumentation panels, and the governing specification or drawing is 8856-E-53, 8856-M-323-C and JG-16, respectively.
3.0 DESCRIPTION
OF DEFICIENCY Recently there have been a few instances on other nuclear projects where the spot welding was observed to be inad-equate resulting in separation of the adjoining members.
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Therefore, on. March 25 & 26, 1978, an inspection was per-formed on the Unistrut member P1004A and its equivalent by Power Strut and B-Line used in the installed electrical raceway and HVAC duct supports. The method of inspection consisted of 'sounding'he members with a ball peen hammer to detect separated spot welds and verification of the se-paration by insertion of a card between the members at the spot welds. The inspection results indicated a rather high incidence of spot welds with inadequate fusion. Therefore, project Quality Assurance (QA) issued Management Corrective Action Report (MCAR) 1-23 on March 28, 1978.
APR 19 '78 085 Q 97 4-0 ANALYSIS OF SAFETY IMPLICATIONS Various combinations and configurations of channel struts have been used in the support systems. Individual members have been designed as composite sections for which the con-nection (spot welding used in this instance) between adjoin-ing channels is essential to car'ry the postulated loads within established design margins. Thus, inadequate fusion at the spot welding may result in inadequate strength, and may adversely affect the safe operation of the plant under design loading conditions.
5.0 CORRECTIVE ACTION Presently, the deficiency has been observed only for the members with side plates spot welded to the side of a channel (Unistrut P-1004A or its Power Strut or B-Line equivalent). However, it appears that the deficiency may be generic and related to spot welding technique and/or procedure, irrespective of the configuration of the members or the manufacturer. Based upon above, the following action is planned:
5.1 For installed supports.
Spot welded members will be evaluated based on inspection and/or testing of r andomly selected representative samples. Members found to contain deficiencies will be either replaced or repaired. Repair procedures, quired, will be developed later.
if re-5.2 Strut members with side plates which are presently being installed.
On the assumption that spot welding may be totally in-effective, replacement of the equivalent weld capacity is being provided as an interim measure. This will con- .
tinue until the scope of the problem is established, test results are evaluated and final repair procedure, if required, is instituted.
5.3 For the strut members at the jobsite which have not yet been fabricated into supports. I This mater ial will be inspected and tested, and will be repaired or returned to the manufacturer, if required.
APR 19'78 08/49 p 5.4 Corrective action to prevent recurrence.
Surveys of the three manufacturing facilities will be conducted to evaluate current welding techniques and procedures and the adequacy of present quality assurance programs. Based upon the findings of these surveys, we will require the ma'nufacturer to institute corrective actions- to provide adequate assurance regarding the quality of spot welding.
6.0 REMARKS Until sufficient data and information are gathered and a pre-liminary assessment based upon this data is made, a firm" date for submittal of a final report can not be established. How-ever, Bechtel expects that this report will be available in June, 1978.