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Category:Letter type:DCL
MONTHYEARDCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-008, Schedule Considerations for Review of the DCPP License Renewal Application2024-01-17017 January 2024 Schedule Considerations for Review of the DCPP License Renewal Application DCL-24-004, Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2024-01-15015 January 2024 Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-129, Nuclear Material Transaction Report for New Fuel2023-12-27027 December 2023 Nuclear Material Transaction Report for New Fuel DCL-23-122, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-14014 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation DCL-23-128, Emergency Plan Update2023-12-13013 December 2023 Emergency Plan Update DCL-23-125, Core Operating Limits Report for Unit 1 Cycle 252023-12-0606 December 2023 Core Operating Limits Report for Unit 1 Cycle 25 DCL-23-121, Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System2023-11-16016 November 2023 Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System DCL-23-120, License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System2023-11-14014 November 2023 License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System DCL-23-118, License Renewal Application2023-11-0707 November 2023 License Renewal Application DCL-2023-520, Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP)2023-10-19019 October 2023 Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP) DCL-23-103, Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System2023-10-13013 October 2023 Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System DCL-23-092, Material Status Report for the Period Ending August 31, 20232023-09-28028 September 2023 Material Status Report for the Period Ending August 31, 2023 DCL-23-077, License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-27027 September 2023 License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors DCL-23-083, Upcoming Meeting with Nuclear Security and Incident Response Staff2023-09-13013 September 2023 Upcoming Meeting with Nuclear Security and Incident Response Staff DCL-23-078, Nuclear Material Transaction Report for New Fuel2023-09-0606 September 2023 Nuclear Material Transaction Report for New Fuel DCL-23-070, Withdrawal of Request Regarding Senior Reactor Operator License Application2023-08-16016 August 2023 Withdrawal of Request Regarding Senior Reactor Operator License Application DCL-23-068, Nuclear Material Transaction Report for New Fuel2023-08-0909 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-066, Nuclear Material Transaction Report for New Fuel2023-08-0303 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-065, Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure2023-07-27027 July 2023 Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure DCL-23-064, Nuclear Material Transaction Report for New Fuel2023-07-26026 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-054, License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-07-13013 July 2023 License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-055, Nuclear Material Transaction Report for New Fuel2023-07-0606 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-042, Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 02023-05-24024 May 2023 Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 0 DCL-23-032, Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program2023-05-22022 May 2023 Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program DCL-23-041, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20222023-05-22022 May 2023 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2022 DCL-23-038, Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule2023-05-15015 May 2023 Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule DCL-23-034, 2022 Annual Nonradiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Nonradiological Environmental Operating Report DCL-23-036, 2022 Annual Radiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Radiological Environmental Operating Report DCL-23-025, 2022 Annual Radioactive Effluent Release Report2023-05-0101 May 2023 2022 Annual Radioactive Effluent Release Report DCL-2023-512, Submittal of Receiving Water Monitoring Program 2022 Annual Report2023-04-27027 April 2023 Submittal of Receiving Water Monitoring Program 2022 Annual Report DCL-23-035, Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application2023-04-24024 April 2023 Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application DCL-23-028, Technical Specification Bases, Revision 142023-04-24024 April 2023 Technical Specification Bases, Revision 14 DCL-2023-511, Report on Discharge Monitoring for the First Quarter of 20232023-04-20020 April 2023 Report on Discharge Monitoring for the First Quarter of 2023 DCL-23-031, Submittal of Annual Report of Occupational Radiation Exposure for 20222023-04-19019 April 2023 Submittal of Annual Report of Occupational Radiation Exposure for 2022 DCL-23-024, Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System2023-04-0404 April 2023 Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System DCL-23-022, 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant2023-03-29029 March 2023 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant DCL-23-023, Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 22023-03-28028 March 2023 Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 2 DCL-23-021, Independent Spent Fuel Storage Installation, Emergency Plan Update2023-03-23023 March 2023 Independent Spent Fuel Storage Installation, Emergency Plan Update DCL-23-020, Responses to NRC Questions Regarding License Renewal Efforts2023-03-17017 March 2023 Responses to NRC Questions Regarding License Renewal Efforts DCL-23-009, Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage2023-02-22022 February 2023 Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage DCL-23-008, Request Regarding Senior Reactor Operator License Application2023-02-22022 February 2023 Request Regarding Senior Reactor Operator License Application DCL-2023-503, Annual Sea Turtle Report2023-01-26026 January 2023 Annual Sea Turtle Report DCL-2023-502, (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring2023-01-18018 January 2023 (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring DCL-22-091, Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage2022-12-20020 December 2022 Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage DCL-22-089, Core Operating Limits Report for Unit 2 Cycle 242022-12-20020 December 2022 Core Operating Limits Report for Unit 2 Cycle 24 DCL-22-085, Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application2022-10-31031 October 2022 Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application DCL-22-041, Site-Specific Decommissioning Cost Estimate, Revision 12022-10-12012 October 2022 Site-Specific Decommissioning Cost Estimate, Revision 1 DCL-22-042, Post-Shutdown Decommissioning Activities Report, Revision 12022-10-12012 October 2022 Post-Shutdown Decommissioning Activities Report, Revision 1 2024-01-29
[Table view] Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23038A0192023-02-0606 February 2023 Curtiss-Wright Part 21 Notification for Qualtech Np Supplied Eaton TMR5 Timing Relays ML20366A0472020-11-18018 November 2020 Curtiss-Wright 10 CFR Part 21 Notification for SF-1154 Hydraulic Fluid Batch 17BLVS293 ML19121A1552019-04-15015 April 2019 Curtiss-Wright Nuclear Division, Enertech - 10 CFR Part 21 Notification for SF-1154 Hydraulic Fluid ML17194A8252017-07-11011 July 2017 Part 21 Report Re Wedge Pin Failure in Anchor Darling Motor Operated Double Disc Gate Valves with Threaded Stem to Upper Wedge Connections ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML16321A4502016-08-31031 August 2016 Part 21 Notification - Flowserve Swing Check Valves ML16125A3602016-04-26026 April 2016 Part 21 - Hydraulic Snubber Seal Material Deviation Interim Report ML15357A0422015-12-18018 December 2015 Curtiss-Wright Corp. - Notification of Part 21 Report on Eaton/Cutler Hammer A200 Series Starters (and Contactors), Per North Anna, H.B. Robinson, Diablo Canyon, and Hatch ML16020A4762015-12-18018 December 2015 Curtiss-Wright Corp. - Notification of Part 21 Report on Eaton/Cutler Hammer A200 Series Starters (and Contactors), Per North Anna, H.B. Robinson, Diablo Canyon, and Hatch ML15205A2892015-07-24024 July 2015 Notification of Part 21 Report - Deviation in Nozzle Modeling Internal Reports ML15188A0662015-06-25025 June 2015 Part 21 Report - Deviation in Nozzle Modeling Internal Reports ML15103A4852015-04-0707 April 2015 Itt Engineered Valves - 2nd Interim Report to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M I Diaphragms, Customer Testing ML14274A0522014-09-22022 September 2014 Final Report 10CFR Part 21 Evaluation Regarding Misaligned Separators in LCR-25 Standby Batteries, Revision 1 - Original Letter Did Not Include the List of Affected Utilities ML14261A1502014-09-17017 September 2014 Interim Report to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M1 Diaphragms, Customer Testing ML14126A5002014-05-0202 May 2014 Part 21 Report Re Check Valves with Missing Jam Nuts ML14113A3702014-04-18018 April 2014 Part 21 - Thomas and Betts Printed Circuit Boards ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve ML12352A1232012-12-13013 December 2012 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML12348A1362012-12-13013 December 2012 Part 21 60-Day Interim Report Notification: Adequacy of Design Change in Am Magne-Blast Circuit Breakers DCL-12-051, Submittal of 10 CFR Part 21 Notification: Scientech/Nus Hand Controller Specification Defect2012-05-22022 May 2012 Submittal of 10 CFR Part 21 Notification: Scientech/Nus Hand Controller Specification Defect ML12123A0902012-04-29029 April 2012 Notification of Potential Part 21 Report - Controllers Did Not Meet Emi/Rfi Guidelines ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12097A3162012-03-0202 March 2012 Part 21 Report - Rosemont Pressure Tranmitters Out of Tolerance Condition ML12066A1182012-03-0202 March 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12058A1412012-02-23023 February 2012 Part 21 Report - Rosemount Nuclear Instruments, Inc., Pressure Transmitter with Nonzero Based Calibrations ML11251A1982011-09-0606 September 2011 Notification Under 10 CFR Part 21 on Certain Rosemount Model 1153 Series B, 1164 and 1154 Series H Pressure Transmitters, May Not Perform Their Intended Safety Function ML1105908922011-02-25025 February 2011 Notification of Potential Part 21 Report Concerning Failure of Actuators Due to Undersized Output Shafts ML1030601022010-10-29029 October 2010 Notification of Potential Part 21 Transfer of Information Concerning Control Components Inc. (CCI) Drag Valves ML1005129082010-02-12012 February 2010 Notification of Potential Part 21 Report Re Interim Report Concerning an Issue in Sump Blockage Generic Tests ML1004801382010-02-12012 February 2010 Interim Report of the Evaluation of a Deviation Pursuant to 10CFR21.21(a)(2) ML0823901062008-08-25025 August 2008 Notification of Potential Part 21 on Failure of F and G Switches ML0809906342008-04-0404 April 2008 Part 21 Notification Regarding Failure to Comply with the Requirements for Dedication of Commercial Grade Items ML0734402112007-12-0707 December 2007 Deficiency Report Part 21 Potential Insufficient Thread Engagement for Certain Pressure Transmitters ML0727504702007-09-21021 September 2007 MPR Associates, Inc. - Report of Defect in Accordance with 10 CFR 21 ML0710002292007-04-0606 April 2007 Rosemount Nuclear Instruments, Inc., Submittal of Notification Under 10 CFR Part 21 for Certain Model 1152 Pressure Transmitters ML0713703092007-03-0707 March 2007 Velan, Inc., Piston Check Cv Information ML0527003602005-09-23023 September 2005 Part 21 Report on Fluke Biomedical Rms, Fluke Radiation Meter Re Basic Component Supplied Which Fails to Comply or Contains as Defect ML0215102952002-05-15015 May 2002 10 CFR 21 Notification - Potential Defect Fan Assemblies for UPS Systems ML0215502492002-05-10010 May 2002 Letter from W. G. Hampton Subject: 10CFR Part 21 Notification-Potenial Defect Involving Fan Assemblies Used in Forced Air Cooled Uninterruptible Power Supply Systems 2023-02-06
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Pacific Gas and Electric Company James R. Becker Diablo Canyon Power Plant Site Vice President Mail Code 104/6 P. O. Box 56 Avila Beach, CA 93424 805.545.3462 May 22,2012 Internal: 691.3462 Fax: 805.545.6445 PG&E Letter DCL-12-051 U.S. Nuclear Regulatory Commission 10CFR21.21 ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Diablo Canyon Unit 1 10 CFR Part 21 Notification: Scientech/NUS Hand Controller Specification Defect Dear Commissioners and Staff; Pacific Gas and Electric Company (PG&E) is submitting the enclosed Part 21 Notification, in accordance with 10 CFR 21.21 (d)(3)(ii), to provide written notification of the identification of a defect. This information was initially reported to the Nuclear '
Regulatory Commission Operations Center on April 29, 2012 (Event Number .
47872). The information provided in the enclosed report meets the reporting requirements of 10 CFR 21.21 (d)(4).
PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this report.
This event did not adversely affect the health and safety of the public.
James R. Becker wrl8/50476172 Enclosure cc/: Diablo Distribution cc/enc: Elmo E. Collins, NRC Region IV Michael S. Peck, NRC Senior Resident Inspector Joseph M. Sebrosky, NRR Project Manager INPO A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway. Comanche Peak. Diablo Canyon. Palo Verde. San Onofre. South Texas Project. Wolf Creek
Enclosure PG&E Letter DCL-12-051 Enclosure 10 CFR Part 21 Notification Scientech/NUS Hand Controller Specification Defect
Enclosure PG&E Letter DCL-12-051 10 CFR Part 21 Notification Scientech/NUS Hand Controller Specification Defect This notification is presented in a format specified in 10 CFR 21.21 (d)(4).
(i) Name and address of the individual or individuals informing the commission:
James R. Becker Site Vice President Diablo Canyon Power Plant Mail Code 104/6 P.O. Box 56 Avila Beach, CA 93424 (ii) Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect.
Facility:
Pacific Gas & Electric Company Diablo Canyon Power Plant 9 Miles NW of Avila Beach Avila Beach, CA 93424 Basic Component which fails to comply or contains a defect:
Four (4) AMS826 and four (4) AMS827 Scientech/NUS Hand Controllers (iii) Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
The controllers were manufactured by Scientech/NUS, a business unit of Curtiss Wright Flow Control Services Corporation.
(iv) Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply.
On March 23, 2012, Scientech/NUS sent a report (Letter Numbers 12-08-B8 and 12-09-BB) to Pacific Gas & Electric Company (PG&E). This report identified that four AMS826 and four AMS827 hand controllers supplied to Diablo Canyon Power Plant (DCPP) had a deviation from the purchase specification. DCPP specified the controllers to be qualified to meet electromagnetic interference (EMI)/radio frequency interference (RFI) emissions and susceptibility in Page 1 of3
Enclosure PG&E Letter DCL-12-051 accordance with NRC Regulatory Guide 1.180, Rev. 1. Contrary to this requirement, Scientech/NUS did not perform the EMI/RFI testing on the AMS826 controllers, and shipped them to DCPP with a Certificate of Conformance to DCPP's specification. Scientech/NUS tested the AMS827 controllers, which failed some of the required testing, but these were shipped to DCPP with a Certificate of Conformance nonetheless. DCPP accepted the controllers based on the Certificates of Conformance, but did not install them.
The inability of these hand controllers to meet the EMI/RFI emissions and susceptibility requirements as set forth in Regulatory Guide 1.180, Rev. 1 could have created a substantial safety hazard if the controllers had been installed for their intended use. Specifically, DCPP intended to install the hand controllers to control auxiliary feed water from the Unit 1 control room and the hot shutdown panel. Following a postulated fire in the control room, plant shutdown would be managed from the hot shutdown panel. In this instance, radios would be used to communicate with operators at the panel. The controllers would be susceptible to EMIIRFI interference and could potentially affect the operators' ability to safely shut down the plant and maintain it in a safe shutdown condition.
(v) The date on which the information of such defect or failure to comply was obtained.
On April 27,2012, PG&E completed its evaluation of the hand controller specification deviation and made an initial report to the Nuclear Regulatory Commission Operations Center on April 29, 2012 (Event Number 47872).
(vi) In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part.
DCPP received four (4) AMS826 and four (4) AMS827 hand controllers, but had never installed them in the plant. DCPP subsequently hired a different vendor to modify the controllers to meet the Regulatory Guide requirements, has properly received them, and is currently installing the controllers for their original intended use.
(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.
Following acceptance of the controllers, DCPP hired a different vendor to modify the controllers to meet Regulatory Guide 1.180, Rev. 1, EMI/RFI requirements, as confirmed by testing. DCPP has properly received them, and is currently installing the controllers for their original intended use.
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Enclosure PG&E Letter DCL-12-051 DCPP issued a Supplier Deficiency Report to Scientech/NUS requiring a cause analysis and corrective actions to prevent recurrence.
(viii) Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.
These controllers were designed and built specifically for use at DCPP. No additional advice is recommended.
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