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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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Report No. 10CFR21-0098, Rev. 3, Amot Thermostatic Valve Element P/N: 9760X ML11336A3692011-12-0101 December 2011 Notification of Potential Part 21 Interim Report on Thermostatic Valve Failure on Palo Verde EDG ML11228A0842011-08-12012 August 2011 Notification of Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1122401422011-08-11011 August 2011 Part 21 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance 2024-09-06
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Text
1 TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHQN ~, (215) 521 51 IP BIOBrlrQnrll'll Penna%"ania
,'976
.Y'ovanber 5, 1976 gnIPHPr rhiLrr2225552rrrl rINHrrtHrdrcrr.
Mr. J. P. O'Reilly Director-Region I U. S. Nuclear Regulatory Qammission 931 Park Avenue King of Prussia, Pennsylvania 19406 SUSQUEHANNA STiRM EU!CZRIC STATICN (SSES)
INTERIM REPORT OF. REPORTABLE DEFIC~Cv DEFECT IN RPV UNIT I2 POTCH HEM'IDE PLATE DOCKET NO: 50-388 LICENSE NO: CPPR-102 ERs 100450/100508 FILE 840-4 PLA-142
Dear Mr. O'Reilly:
This relates to a deficiency resulting fram a defect in the RPV Unit I2 bottom head side plate. The contractor has reported that the defect was caused during the rEmoval of a ten~rary support strut. The deficiency was evaluated and reported to Mr. Mattia on October 1, 1976 as being of such conseauence as to be considered as a significant deficiency in construc-tion and, therefore, reportable urger the provisions described in 10CFR Part 50.55 (e), (iii).
The impact of this defect is being analyzed by PL, its,contractors, ard a technical consultant, and will be fully addressed in the final, definitive report regarding the deficiency. It is anticipated that the definitive report will be sukmitted within 30 days aft'er the defect has been raroved and blended.
Should it become apparent that this schedule cannot be met, you will be pnxnptly advised.
The following is an account of the relevant details of the deficiency, the investigation pursued and the data which have been established to date:
A. Chronology of Events
- 1. The defect in the BPV Unit I2 bottcm head siae plate is believed to have been created about four months ago when a temporary attachment between the vessel and the support skirt was bL22ned off according to CBI Procedure LBP-1.
P ENN 5 YL VAN I A POWER 8 L I GH T COMPANY
0
'I P
Mr. J. P. O'Reilly Page 2 Novanber 5, 1976
- 2. Due to manpower considerations, the clean up of the attachnent area was delayed until Septanber 28, 1976. In the interim, the activity was under the control of Travel Folder RZK-20, Itan 21A. On Septanber 28, 1976, CBI personnel began rennving metal in the area of the defect. Remrk is allowed by GE Specification 21A9340 which provides for excavation of surface defects to determine their depth.
- 3. The area was excavated to a depth of 15/16" and on Septanber 29, 1976 CBI entered the condition as a defect in their Nonconformance lag.
- 4. On Septanber 30, 1976, GE San Jose notified PL of the defect. After evaluation of the incident, PL unsuccessfully attanpted to reach Mr. Heishnan of NRC Region I at 3:00 p.m. A message was left to return the call.
- 5. Mr. Mattia returned the call at 8:05 a.m. on October 1, 1976 and was advised of the incident. He was informed that the reportability of the defect was being evaluated, and that an interim report or final definitive report, Ncvanber 1, 1976.
if warranted, auld be suhnitted to the NRC by
- 6. On Novanber 1, 1976, PL advised Mr. Mattia that the evaluation was not complete a+2 asked for an extension of the report date until November 8, 1976. This extension was granted.
B. Anal is of Safe lications
- l. Evaluation of the impact of 'the depth of the defect on the nominal material thickness including reconciliation of the thickness reduction with the stxess report is being pursued.
- 2. The consideration of low cycle, high stress fatigue, due to thermal stress or deterioration of the microstxucture within the heat affected zone is being 'studied from a metallurgical aspect.
C. Corrective Measures Taken
- l. On October 10, 1976 CBI issued Request For Acceptance Of Nonconformity As A Deviation (RAD) N8.
- 2. A specific remrk procedure is being prepared to govern the operation.
It is anticipated that the area will be excavated to sound base metal, contour blended, examined by nondestructive examination, acid etched to detexmine that the heat affected zone has been ranoved, and then final inspected.
D. Conclusion This deficiency was discovered during a routine work operation and the inspection activity is under the control of the CBI Quality Assurance Program. This control is assured by the use of the CBI traveler folder which is sequenced such that work will mt progress until the defect is properly dispositioned.
Mr. J. P. O'Reillv Page 3 Novanber 5, 1976 The disposition of the defect is being given full design consideration, including the technical services of a metallurgical consultant. Remrk will be done in accordance with applicable code and regulatory recuire-ments and will be monitored by PL to assure canpliance.
In the interim, the Cczmission will be advised of any significant issue which may arise.
Very truly yours, N. W. Curtis Vice president Eng-ineering e Gcnstructicn JZJ:mcb cc: Mr. Ernst Volgenau (15) Mr. G. McDonald Director Director Office of Inspection and Enforcement Office of Management Infoxmation U.S. Nuclear Regulatory Camnission and Pnxp:am Control Washington, D.C. 20555 U.S. Nuclear Regulatory Gmmission Washington, D.C. 20555