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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML15134A0172015-05-0101 May 2015 Part 21 Report Regarding Potential Test Induced Defect in a 0867F Main Steam Safety Relief Valves ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV 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 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 ML1127000672011-09-26026 September 2011 GE-Hitachi Part 21 Reportable Condition Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML1025202192010-09-0303 September 2010 Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1006213312010-02-24024 February 2010 10CFR21 Reporting of Defects and Non-Compliance, Thomas & Betts Printed Circuit Board P/N 90-41-974313 ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0505602372005-02-16016 February 2005 Letter, Submittal of Potential non-conformance of Diaphragm Disc Used in Certain Asco Scram Pilot Valves and Rebuild Kits 2017-03-20
[Table view] Category:Letter
MONTHYEARIR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report IR 05000354/20220062023-03-0101 March 2023 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2022006) LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023 Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 IR 05000354/20220042023-01-24024 January 2023 Integrated Inspection Report 05000354/2022004 LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023 In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments ML22335A0412022-12-0101 December 2022 Notification of Commercial Grade Dedication Inspection (05000354/2023011) and Request for Information IR 05000354/20220032022-11-0303 November 2022 Integrated Inspection Report 05000354/2022003 2024-02-01
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50 Hanover Road, Florham Park, NJ 07932 ASCon A Constant Flow Of Ideas
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Tel: 973-966-2000
- Fax: 973-966-2628 *www.ascovalve.com Feb 16, 2005 Documents Control Desk United States Nuclear Regulatory Commission Washington, DC 20555
Subject:
P6tential n6i-6coifo rn-ance of diaphragm disc used i certain ASCOsc~rami pilot valves and rebuild kits Gentlemen:
We enclose information relating to diaphragm discs used in certain ASCO scram pilot valves and rebuild kits As you will see from the enclosed materials, there is the possibility of a manufacturing deficiency with these discs, which may affect the operation of the scram pilot valves. ASCO was alerted to this problem upon evaluation of a disc removed from one of several valves undergoing accelerated life tests in ASCO's laboratory. All affected scram pilot valves and rebuild kits were sold to GE Energy. We have notified GE of this potential problem.
As described in the attached, all 31 rebuild kits hav6 been returned to ASCO for'correction and ASCO is performing accelerated life tests to qualify the valves,'installed at Hope Creek, for continued service until such time as they can be conveniently replaced.
ASCO does not have adequate knowledge of the actual installation and operating conditions of these valves to determine whether their malfunction could create a.!substantial safety hazard" as defined in 10CFR21.3. We are likewise unable to conduct the evaluation necessary to make such a determination. Nevertheless, we furnish this information to keep you apprised of our investigation.
Should you wish to discuss this further, or obtain any additional information, please let us know.
Should any additional information become available we will forward it to you.
Very truly yours, ASC VALVE, Inc.
Ro ert . Kem Jr.
Vice-President Sales and Marketing Enclosure
. 4..<. -6 / 19, Oriy*%MC .mm plotval~ves r~otficatoni21' .4AAM pag 211M0 9.54 aeIo I of3
4z POTENTIAL NON-CONFORMANCE OF DIAPHRAGM DISC USED IN CERTAIN ASCO SCRAM PILOT VALVES AND REBUILD KITS NAME AND ADDRESS OF INDIVIDUAL INFORMING THE COMMISSION:
Robert W. Kemple Jr.
Vice-President Sales & Marketing ASCO VALVE, Inc.
50 Hanover Road Florham Park, NJ 07932
-IDENTIFICATION OF THE ITEMS SUPPLIED: _ _ _ _
Diaphragm disc, ASCO part number 103889-013. supplied as a component of 31 rebuild kits, ASCO 316929 and 14 Scram Pilot Valves, ASCO HV268000-001, sold to GE Energy.
NATURE OF THE FAILURE AND POTENTIAL SAFETY HAZARD:
These discs are from a lot received at ASCO in May of 2004. The non-conformance was discovered during evaluation of a disc, from the May, 2004 receipt, removed from one of several valves undergoing accelerated life tests in ASCO's laboratory. The valve from which the disc was removed had been aged the equivalent of 40 years. A TGA (Thermogravimetric Analysis) was performed on the disc material. The TGA results suggested that the material was non-conforming because the values exceeded those specified on the disc drawing. Specifically, the drawing calls for weight loss on the TGA to be less than 0.2%. (Ref. ASCO Valve Engineering Data Sheet 226). The TGA on the tested disc had a weight loss of 1.4% when tested in the ASCO Valve Q.A. lab. Two of the remaining valves on life test were disassembled and TGAs performed on one of the diaphragm discs from each. Weight loss for both was approximately .7%. Both of these discs were from the May, 2004 lot.
A review of the receiving records for the parts revealed that for the lot received in May 2004, a TGA test had not been performed during incoming inspection at ASCO, nor had it been performed by the vendor as required by ASCO. This was the result of equipment problems at the vendor and an oversight at ASCO's incoming inspection. A review of receiving records revealed that all previous receipts of diaphragm discs had been properly tested and documented in accordance with ASCO drawings and procedures, and were
.. withinspecification _____________-
ASCO also performed TGA testing on a diaphragm disc from the May, 2004 lot that had not been exposed to testing, which essentially represented an "as received" part. The results of this test revealed TGA values in excess of those specified on the disc drawing. Values ranged from .5%to .7%.
To insure the accuracy of the TGA readings, the test equipment manufacturer (TA) was brought in to review the test methodology and evaluate the test equipment for accuracy. TA found that our test methodology was acceptable, and accuracy of the equipment was found to be within .1%.
Although ASCO is unable to determine if this non-conformance would have an adverse affect on valve performance, there is the possibility that this non-conformance could result in degradation of valve response time or, in worst case, failure of the diaphragm to move off the valve seat. It was, therefore, our recommendation that this product be retrieved from the field and replaced with product incorporating conforming discs.
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I . Z THE CORRECTIVE ACTION WHICH IS BEING TAKEN:
All 31 rebuild kits containing diaphragm discs from the May 2004 lot have been returned to ASCO from GE's inventory and will be replaced. 10 of the 14 valves that included discs from the May 2004 lot have been installed at Hope Creek Nuclear Power Generating Station. ASCO has begun accelerated qualification testing to determine if the installed valves can remain in operation until they can be conveniently replaced. We expect the results of this testing to be available week ending Feb. 18, 2005.
The 4 uninstalled valves will be returned to ASCO for retrofit.
We are working with our disc vendor to determine why they produced apparently non-conforming parts, and what they have to do to produce conforming parts. They have put additional controls in place, including multiple sign-offs on shop orders to insure required testing has been performed and properly documented prior to shipment.
-- ASCO's'operation sheet for this part'has been revised'c to-incLede-he-reqcirein6nnthGtTGA;nd - otheir required tests be performed on each lot, and to include the requirement that the vendor must supply their test results with the material. Inaddition, the disc drawing will be changed to include the requirement that the vendor provide their test results for each lot and that ASCO must perform TGA and other required tests testing on each lot.
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