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| #REDIRECT [[NOC-AE-20003730, Withdrawal of Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-02)]] | | {{Adams |
| | | number = ML20128J902 |
| | | issue date = 05/07/2020 |
| | | title = Withdrawal of Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-02) |
| | | author name = Dunn R |
| | | author affiliation = South Texas Project Nuclear Operating Co |
| | | addressee name = |
| | | addressee affiliation = NRC/Document Control Desk, NRC/NRR |
| | | docket = 05000498, 05000499 |
| | | license number = |
| | | contact person = |
| | | case reference number = 35013752, EPID L2020-LLR-0008, NOC-AE-20003730 |
| | | document type = Letter |
| | | page count = 1 |
| | | project = EPID:L2020 |
| | | stage = Withdrawal |
| | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:May 7, 2020 NOC-AE-20003730 10 CFR 50.55a(z) |
| | STI: 35013752 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Withdrawal of Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-02) (EPID: L 2020-LLR-0008) |
| | |
| | ==Reference:== |
| | : 1. Letter; from R. Dunn to U.S. NRC Document Control Desk; "Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-02)"; |
| | January 22, 2020; (NOC-AE-20003701) (ML20022A319). |
| | The purpose of this letter is to withdraw South Texas Project (STP) Units 1 and 2 Relief Request PRR-02 (EPID: L 2020-LLR-0008). In Reference 1, STP Nuclear Operating Company (STPNOC) requested an alternative to the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) 2012 Edition for use during the fourth ten-year Inservice Test (IST) interval at South Texas Project. |
| | On April 15, 2020, Regulatory Guide (RG) 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 3, was incorporated by reference into the NRCs regulations. Code Case OMN-16 Revision 2, Use of a Pump Curve for Testing, 2017 Edition was addressed in RG 1.192, Table 1 of Code Cases, which the NRC approves for use without conditions. |
| | Incorporation of this ASME OM Code case removes the necessity for an alternative request. |
| | There are no new commitments in this letter. |
| | If there are any questions regarding this withdrawal, please contact me at 361-972-7743 or N. Boehmisch at 361-972-8172. |
| | Roland Dunn General Manager, Engineering NB cc: |
| | Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 E. Lamar Boulevard Arlington, TX 76011-4511}} |
Letter Sequence Withdrawal |
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EPID:L2020, GE-Hitachi Global Laser Enrichment LLC Revised Request for Termination of License No. SNM-2019, Docket No. 70-7016 (Withdrawn, Closed) |
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MONTHYEARML20105A4602020-04-16016 April 2020 Letter, Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (Exigent Circumstances) Project stage: Other ML20128J9022020-05-0707 May 2020 Withdrawal of Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-02) Project stage: Withdrawal ML20282A5672020-08-25025 August 2020 GE-Hitachi Global Laser Enrichment LLC Revised Request for Termination of License No. SNM-2019, Docket No. 70-7016 Project stage: Request RS-20-110, Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-09-0202 September 2020 Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI Project stage: Request ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 Project stage: Other ML20293A1742021-01-0505 January 2021 Termination of Special Nuclear Materials License Number SNM-2019 for the Ge-Hitachi Global Laser Enrichment Facility (Enterprise Project Identification Number: L-2020- DTP-0000) Project stage: Request ML21026A0482021-01-29029 January 2021 Announcement of Change in Authorizing Official Facility Clearance for the Global Laser Enrichment (Gle) Facility (Enterprise Project Identification Number: L2020-NEW-0007) Project stage: Other NOC-AE-21003784, Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing2021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing Project stage: Response to RAI ML21067A7722021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing Project stage: Response to RAI ML21130A2192021-05-10010 May 2021 Request for Additional Information Regarding Steam Generator Tube Inspection Reports (EPIDs L2020-LRO-0055, L-2020-LRO-0082, and L2020-LRO-0083) Project stage: Request ML21281A0472021-08-10010 August 2021 Orano NCS Gmbh - Answers to Rsis for the Review of the DN30-X Package Project stage: Other ML21281A0482021-10-0808 October 2021 Orano NCS Gmbh - Application for Withholding Proprietary Information from Public Disclosure Project stage: Request ML22252A0372022-09-0909 September 2022 Orano NCS Gmbh - Answers to RAIs for the Review of the DN30-X Package Project stage: Other 2021-01-29
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Category:Letter
MONTHYEARML24304B0512024-10-30030 October 2024 Cycle 26 Core Operating Limits Report IR 05000498/20244022024-10-23023 October 2024 Security Baseline Inspection Report 05000498/2024402 and 05000499/2024402 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function ML24295A0772024-10-21021 October 2024 Licensed Operator Positive Fitness-for-Duty Test 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24290A1162024-10-16016 October 2024 Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan ML24255A0322024-09-30030 September 2024 The Associated Independent Spent Fuel Storage Installation - Notice of Consideration of Approval of Direct Transfer of Licenses and Opportunity to Request a Hearing (EPID L-2024-LLM-0002) - Letter ML24269A1762024-09-25025 September 2024 Tpdes Permit Renewal Application WQ0001 908000 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps ML24271A3022024-09-18018 September 2024 STP-2024-09 Post-Exam Comments - Redacted ML24274A0902024-09-16016 September 2024 Written Response - EA-24-026 STP Operator - Redacted ML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators IR 05000498/20243012024-08-27027 August 2024 NRC Initial Operator Licensing Examination Approval 05000498/2024301; 05000499/2024301 IR 05000498/20240052024-08-22022 August 2024 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005) IR 05000498/20240022024-08-0909 August 2024 Integrated Inspection Report 05000498/2024002 and 05000499/2024002 IR 05000498/20240102024-08-0808 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010 ML24218A1462024-07-26026 July 2024 2. EPA Comments on South Texas Project Exemption Ea/Fonsi ML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2842024-05-15015 May 2024 Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance ML24137A0882024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24128A1572024-05-0707 May 2024 Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000498/20240012024-05-0606 May 2024 Integrated Inspection Report 05000498/2024001 & 05000499/2024001 ML24120A3762024-04-29029 April 2024 Annual Dose Report for 2023 ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24117A1602024-04-24024 April 2024 2023 Radioactive Effluent Release Report ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24113A3122024-04-22022 April 2024 Cycle 24 Core Operating Limits Report ML24097A0072024-04-0606 April 2024 Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24088A3022024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update ML24081A3972024-03-21021 March 2024 Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NOC-AE-240040, Nuclear Liability Certificates of Insurance2024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24066A2002024-03-0606 March 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML24079A1312024-03-0505 March 2024 Nuclear Insurance Protection ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 IR 05000498/20230062024-02-28028 February 2024 Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006) IR 05000498/20240132024-02-27027 February 2024 Design Basis Assurance Inspection (Programs) Commercial Grade Dedication IR 05000498/2024013 and 05000499/2024013 ML24022A2252024-02-20020 February 2024 Issuance of Amendment Nos. 227 and 212 to Authorize the Revision of the Alternative Source Term Dose Calculation ML24050A0082024-02-19019 February 2024 Evidence of Financial Protection 2024-09-30
[Table view] |
Text
May 7, 2020 NOC-AE-20003730 10 CFR 50.55a(z)
STI: 35013752 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Withdrawal of Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-02) (EPID: L 2020-LLR-0008)
Reference:
- 1. Letter; from R. Dunn to U.S. NRC Document Control Desk; "Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-02)";
January 22, 2020; (NOC-AE-20003701) (ML20022A319).
The purpose of this letter is to withdraw South Texas Project (STP) Units 1 and 2 Relief Request PRR-02 (EPID: L 2020-LLR-0008). In Reference 1, STP Nuclear Operating Company (STPNOC) requested an alternative to the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) 2012 Edition for use during the fourth ten-year Inservice Test (IST) interval at South Texas Project.
On April 15, 2020, Regulatory Guide (RG) 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 3, was incorporated by reference into the NRCs regulations. Code Case OMN-16 Revision 2, Use of a Pump Curve for Testing, 2017 Edition was addressed in RG 1.192, Table 1 of Code Cases, which the NRC approves for use without conditions.
Incorporation of this ASME OM Code case removes the necessity for an alternative request.
There are no new commitments in this letter.
If there are any questions regarding this withdrawal, please contact me at 361-972-7743 or N. Boehmisch at 361-972-8172.
Roland Dunn General Manager, Engineering NB cc:
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 E. Lamar Boulevard Arlington, TX 76011-4511