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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARDCL-24-083, CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated2024-09-0909 September 2024 CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated DCL-24-056, Part 21 Interim Report Re Emergency Diesel Generator Fuel Snubber Valve Assembly2024-05-28028 May 2024 Part 21 Interim Report Re Emergency Diesel Generator Fuel Snubber Valve Assembly ML23038A0192023-02-0606 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 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 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 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 ML12348A1362012-12-13013 December 2012 Part 21 60-Day Interim Report Notification: Adequacy of Design Change in Am Magne-Blast Circuit Breakers ML12352A1232012-12-13013 December 2012 60-Day Interim Report Involving an Evaluation of a Design Change to 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 2024-09-09
[Table view] Category:Letter type:DCL
MONTHYEARDCL-24-087, License Renewal - Historic and Cultural Resources Reference Documents (Redacted)2024-09-12012 September 2024 License Renewal - Historic and Cultural Resources Reference Documents (Redacted) DCL-24-083, CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated2024-09-0909 September 2024 CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated DCL-24-078, Pre-Notice of Disbursement from Decommissioning Trust2024-09-0303 September 2024 Pre-Notice of Disbursement from Decommissioning Trust DCL-24-082, Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment2024-08-28028 August 2024 Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment DCL-24-077, Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident2024-08-15015 August 2024 Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident DCL-24-075, Response to Request for Additional Information for 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 React2024-08-0808 August 2024 Response to Request for Additional Information for 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 React DCL-24-070, License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2024-07-31031 July 2024 License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies DCL-24-071, Core Operating Limits Report for Unit 2 Cycle 252024-07-22022 July 2024 Core Operating Limits Report for Unit 2 Cycle 25 DCL-2024-523, Submittal of Report on Discharge Self-Monitoring2024-07-18018 July 2024 Submittal of Report on Discharge Self-Monitoring DCL-2024-527, Sea Turtle Stranding Report (Loggerhead Sea Turtle) Diablo Canyon Power Plant2024-07-0101 July 2024 Sea Turtle Stranding Report (Loggerhead Sea Turtle) Diablo Canyon Power Plant DCL-24-066, Request to Extend the Nrg Approval of Alternative for Use of Full Structural Weld Overlay, REP-RHR-SWOL2024-06-27027 June 2024 Request to Extend the Nrg Approval of Alternative for Use of Full Structural Weld Overlay, REP-RHR-SWOL DCL-24-052, Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report2024-05-16016 May 2024 Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report DCL-24-051, One Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage2024-05-0808 May 2024 One Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage DCL-24-049, 2023 Annual Radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Radiological Environmental Operating Report DCL-24-047, 2023 Annual Non-radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Non-radiological Environmental Operating Report DCL-24-048, O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 20232024-04-30030 April 2024 O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 2023 DCL-24-027, 2023 Annual Radioactive Effluent Release Report2024-04-28028 April 2024 2023 Annual Radioactive Effluent Release Report DCL-24-045, Annual Report of Occupational Radiation Exposure for 20232024-04-24024 April 2024 Annual Report of Occupational Radiation Exposure for 2023 DCL-24-042, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-04-17017 April 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations DCL-24-022, Notification of Changes to Decommissioning Schedule2024-04-0202 April 2024 Notification of Changes to Decommissioning Schedule DCL-24-023, Revised Certification of Permanent Cessation of Power Operations2024-04-0202 April 2024 Revised Certification of Permanent Cessation of Power Operations DCL-24-031, Decommissioning Funding Report2024-03-27027 March 2024 Decommissioning Funding Report DCL-24-032, 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant2024-03-27027 March 2024 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant DCL-24-028, Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability2024-03-21021 March 2024 Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability DCL-24-018, License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2024-02-28028 February 2024 License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) DCL-2024-507, 2023 Annual Report on Discharge Self-Monitoring2024-02-27027 February 2024 2023 Annual Report on Discharge Self-Monitoring DCL-24-020, Nuclear Material Transaction Report for New Fuel2024-02-21021 February 2024 Nuclear Material Transaction Report for New Fuel DCL-24-014, Owners Activity Report for Unit 1 Twenty-Fourth Refueling Outage2024-02-12012 February 2024 Owners Activity Report for Unit 1 Twenty-Fourth Refueling Outage DCL-24-013, Nuclear Material Transaction Report for New Fuel2024-02-0707 February 2024 Nuclear Material Transaction Report for New Fuel DCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel DCL-2024-502, 2023 Annual Sea Turtle Report for Diablo Canyon Power Plant (DCPP)2024-01-25025 January 2024 2023 Annual Sea Turtle Report for Diablo Canyon Power Plant (DCPP) DCL-2024-501, Sea Turtle Stranding Report (Green Sea Turtle)2024-01-24024 January 2024 Sea Turtle Stranding Report (Green Sea Turtle) DCL-2024-500, Transmittal of the 4th Quarter of 2023 Report on Discharge Self-Monitoring2024-01-18018 January 2024 Transmittal of the 4th Quarter of 2023 Report on Discharge Self-Monitoring 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-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel 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 2024-09-09
[Table view] |
Text
Pac ific Gas and Electric Company "'
Adam S. Peck Oia blo Can y on Po wer Plan t Site Vi ce President Mail cod e 10416/605 P.O. Bo x 56 Avila Bea c h, CA 93424
805.545. 6675 Adam. Pec k@pge.co m
PG&E Letter DCL-24-083 10CFR21.21
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 10 CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated
Dear Commissioners and Staff:
In accordance with the requirements of 10 CFR 21.21 (d)(3)(ii), Pacific Gas and Electric Company (PG&E) hereby submits the enclosed Diablo Canyon Power Plant (DCPP) written notification regarding a commercially dedicated snubber valve assembly. This information was initially reported to the Nuclear Regulatory Commission Operations Center on August 15, 2024 (Event Notification 57271 ).
PG&E makes no new or revised regulatory commitments (as defined by NEI 99-
- 04) in this report. Corrective actions identified in this letter will be implemented in accordance with the DCPP Corrective Action Program.
If you have any questions or require additional information, please contact Mr. James Morris, Manager, Regulatory Services, at (805) 545-4609.
Sincerely,
- ~ '>,...:.....,.::r.._,. _ -
September 9, 2024 Adam S. Peck Date
dqmg/51231137 Enclosure cc/enc: Diablo Distribution Mahdi 0. Hayes, NRG Senior Resident Inspector INPO Samson S. Lee, NRR Senior Project Manager John D. Monninger, NRC Region IV Administrator
A m e m ber of the ST ARS Allian c e Ca lla w ay
10 CFR PART 21 NOTIFICATION
Commercially Dedicated Snubber Valve Not Properly Heat Treated Enclosure PG&E Letter DCL-24-083
10 CFR Part 21 Notification ALCO Snubber Valve
The following information is provided pursuant to 10 CFR 21.21 (d)(4).
- i. Name and Address of the individual or individuals informing the Commission:
Adam S. Peck Site Vice President and Acting Chief Nuclear Officer Diablo Canyon Power Plant Mail code 104/6/605 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: Diablo Canyon Power Plant (DCPP) Units 1 and 2 Docket No. 50-275 and 50-323 License No. OL-DPR-80 and OL-DPR-82 Basic Component: ALCO Snubber Valve Part Number 2402466
iii. Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect:
Pacific Gas and Electric (PG&E) Company Diablo Canyon Power Plant P.O. Box56 Avila Beach, CA 93424
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 September 12, 2023, DCPP identified the apparent failure of a snubber valve assembly during a routine surveillance test. The snubber valve was removed and replaced. This condition did not impact the operability of any safety related systems or impact the health and safety of the public.
The failed snubber valve had originated from a specific lot of ALCO Snubber Valves (Part Number 2402466), which were purchased as a commercial-grade
Page 1 of 3 Enclosure PG&E Letter DCL-24-083
item and dedicated by PG&E solely for use at DCPP. The dedication of the subject lot (Part Number 2402466) was completed during July 2008.
PG&E performed a 10 CFR Part 21 evaluation and determined that reporting in accordance with Part 21.21 was required for these ALCO snubber valve assemblies. The upper body of the valves had been subjected to improper case hardening of the concave seating surface and were manufactured from incorrect material (AISI 1117 resulfurized carbon steel vs. AISI 8620/8630).
The improper case-hardening and the incorrect material application can result in micro-cracking in the tip of the snubber valve, which can expand and cause insufficient flow through the valve.
- v. The date on which the information of such defect or failure to comply was obtained:
On May 28, 2024, PG&E informed the Nuclear Regulatory Commission (NRC) that it had initiated a 10 CFR Part 21 evaluation of a deviation concerning commercial-grade item dedicated at DCPP via an interim Part 21 report. After PG&E completed its evaluation, the reporting officer was subsequently informed on August 13, 2024. The defect was reported to the NRC telephonically on August 15, 2024 (Event Notification 57271 ).
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:
The snubber valve assemblies (Part Number 2402466) in question were removed from unrestricted spares and underwent further material analyses.
They were subsequently discarded. None of these snubber valve assemblies have been provided by PG&E to any other stations or vendors.
Two fuel snubber valve assemblies from the same material batch remain installed in the plant. PG&E has performed an assessment and determined they do not affect the operability of any safety related systems. There is no risk to the health and safety of the public.
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:
Page 2 of 3 Enclosure PG&E Letter DCL-24-083 As stated in the response to question vi, the subject non-installed snubber valve assemblies have been discarded. The associated dedication package has been deleted and PG&E intends to purchase future snubber valve assemblies as safety-related.
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:
This issue was documented in the DCPP corrective action program. As stated above, the subject snubber valve assemblies were purchased as a commercial grade item under ALCO Part No. 2402466 and dedicated for a safety-related application. Utilities that perform this dedication should consider specific tests for case-hardening and correct material verification.
Also note that similar issues have been reported to the NRG:
CORPORATION/ FACILITIY: Entergy/ Palisades NOTIFICATION DATE: March 13, 2008 EVENT NUMBER: 44059
- ALCO Part Number 240466
- AISI E 52100 material composition
CORPORATION/ FACILITIY: Fairbanks Morse I Not Applicable NOTIFICATION DATE: April 29, 2008 EVENT NUMBER: 44178
-ALCO Part Number 2402466-1
- Material composition not specified in report
Based on the snubber valve history supported by these two reports, licensees should review their purchase order and installation history for snubber valves purchased ahead of and during the 2008 timeframe for similar vulnerabilities.
ix. In the case of an early site permit, the entities to whom an early site permit was transferred:
Not applicable.
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