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| | number = ML16271A467 | | | number = ML16271A467 |
| | issue date = 09/27/2016 | | | issue date = 09/27/2016 |
| | title = South Texas Project Electric Generating Station, Units 1 And 2 - Notification Of An NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000498/2017007 and 05000499/2017007) And Request For Information | | | title = South Texas Project Electric Generating Station, Units 1 And 2 - Notification Of An NRC Triennial Fire Protection Baseline Inspection (Nrc Inspection Report 05000498/2017007 and 05000499/2017007) And Request For Information |
| | author name = Werner G E | | | author name = Werner G E |
| | author affiliation = NRC/RGN-IV/DRS/EB-2 | | | author affiliation = NRC/RGN-IV/DRS/EB-2 |
Revision as of 00:25, 13 February 2018
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Category:Inspection Report Correspondence
MONTHYEARML17103A6272017-04-13013 April 2017 Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000498/2017007 and 05000499/2017007) and Request for Information ML16271A4672016-09-27027 September 2016 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000498/2017007 and 05000499/2017007) and Request for Information NOC-AE-16003325, Company Response to Inspection Report 05000498/2014406 and 05000499/2014406: Cover Letter2016-04-14014 April 2016 Company Response to Inspection Report 05000498/2014406 and 05000499/2014406: Cover Letter IR 05000498/20154022016-03-0202 March 2016 Non-Public Security Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (NRC Physical Security Inspection Report Numbers 05000498/2015402 and 05000499/2015402) IR 05000498/20114032011-04-0808 April 2011 NRC Security Inspection Report 05000498-11-403 and 05000499-11-403, Cover Letter Only IR 05000498/20105012011-01-10010 January 2011 IR 05000498-10-501 and 05000499-10-501, on 12/31/2010, South Texas Project Electric Generating Station, Unit 1 and 2 - NRC Emergency Preparedness Annual IR 05000498/20094042010-06-0909 June 2010 NRC Integrated Inspection Report 05000498-09-404 and 05000499-09-404 Errata IR 05000498/20094012010-03-26026 March 2010 NRC Physical Security Annual Inspection Report 05000498-09-401 and 05000499-09401 ML0804505912008-02-13013 February 2008 IR 05000498-08-003 and 05000499-08-003, on 04/07-18/2008, South Texas Project Electric Generating Station, Unit 1 and 2 - Notification of Inspection and Request for Information IR 05000498/20060102006-11-0808 November 2006 IR 05000498-06-010, IR 05000499-06-010, on 09/25-28/2006, South Texas Project, Units 1 & 2, 95001 Supplemental Inspection IR 05000498/20010082002-04-12012 April 2002 IR 05000498/2001-008; IR 05000499/2001-008; on 12/29/2001 - 3/23/2002; STP Nuclear Operating Company; South Texas Project Electric Generating Station; Units 1 & 2. Integrated Res/Reg Rpt; Event Fwp, Problem Identification and Reporting IR 05000498/20010062002-01-24024 January 2002 IR 05000498/2001-006 and IR 05000499/2001-006;STP Nuclear Operating Company, Inspection on 09/23-12/29/2001, Related to Integrated Res/Reg Rpt; Event Fwp, Emergency Action Level and Plan Changes, & Access Control to Radiologically Significa IR 05000498/20010042002-01-14014 January 2002 IR 05000498/2001-004, IR 05000499/2001-004, STP Nuclear Operating Company, South Texas Project Units 1 & 2, Inspection on 11/05-12/07/2001 Re Safety System Design, Performance Capability, Evaluation of Changes, Tests, or Experiments. Violat IR 05000498/20010102002-01-11011 January 2002 IR 05000498/2001-010, IR 05000499/2001-010, STP Nuclear Operating Company, South Texas Project Electric Generating Station, Units 1& 2, Special Team Inspection on 12/18/2001 - 12/21/2001. Corrective Actions, Event Response 2017-04-13
[Table view] 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 05000498/20240052024-08-22022 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 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 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 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 ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report 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 ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance NOC-AE-240040, Nuclear Liability Certificates of Insurance2024-03-19019 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 ML24045A0922024-02-16016 February 2024 Response to STP FOF Move Letter (2024) 2024-09-30
[Table view] |
See also: IR 05000498/2017007
Text
September 27, 2016
Mr. Dennis Koehl President and Chief Executive Officer STP Nuclear Operating Company P.O. Box 289 Wadsworth, TX 77483
SUBJECT: SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION, UNITS 1 AND 2 - NOTIFICATION OF AN NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT 05000498/2017007 AND 05000499/2017007) AND REQUEST FOR INFORMATION
Dear Mr. Koehl:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC), Region IV staff will conduct a triennial fire protection baseline inspection at the South Texas Project Electric Generating Station, Units 1 and 2, in January and February 2017. The inspection team will be comprised of four reactor inspectors from the NRC Region IV office.
The inspection will be conducted in accordance with Inspection Procedure 71111.05T, "Fire Protection (Triennial)," the NRC's baseline fire protection inspection procedure. The schedule for the inspection is as follows:
- Information gathering visit: January 4-5, 2017 * On-site inspection: January 23-27, 2017 February 6-10, 2017 The purpose of the information gathering visit is to obtain information and documentation needed to support the inspection and to become familiar with the fire protection program, fire protection features, post-fire safe shutdown capabilities, plant layout, and mitigating strategies to address Section B.5.b of NRC Order EA-02-026, "Order for Interim Safeguards and Security Compensatory Measures," dated February 25, 2002, and 10 CFR 50.54(hh)(2).
One inspector will participate in the information gathering visit to select the fire areas for evaluation, identify additional documents needed to support the inspection, obtain unescorted access, and meet with the key personnel who will support the inspection. The fire area selection will require a walkdown of candidate fire areas in company with key personnel from your staff. The enclosure to this letter provides an initial list of the documents the team will need for their review. We request that your staff transmit copies of the documents listed in the enclosure to the NRC Region IV office for team use in preparation for the inspection. Please send this information so that it will arrive in the NRC Region IV office by the dates listed in the enclosure.
During the information gathering visit, the team will also discuss the following inspection support administrative details: office space size and location, specific documents requested to be made available to the team in their office spaces, arrangements for reactor site access, and the availability of knowledgeable plant engineering and licensing organization personnel to serve as points of contact during the inspection.
We request that during the on-site inspection weeks, you ensure that copies of analyses, evaluations, or documentation regarding the implementation and maintenance of the fire protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest for the fire protection portion of the inspection are those documents that establish that your fire protection program satisfies the NRC regulatory requirements and conforms to applicable NRC and industry fire protection guidance. For the B.5.b portion of the inspection, those documents implementing your mitigating strategies and demonstrating the management of your commitments for the strategies are of specific interest. Also, please ensure that appropriate personnel are available to support the team at the site during the inspection. These personnel should be knowledgeable of the plant systems required to achieve and maintain safe shutdown conditions from inside and outside the control room, the electrical aspects of the post-fire safe shutdown analyses, the reactor plant fire protection systems, and the fire protection program and its implementation.
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget under control number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice and Procedure," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Your cooperation and support during this inspection will be appreciated. If you have questions concerning this inspection or the inspection team's information or logistical needs, please contact Samuel Graves, the team lead inspector, in the Region IV office at (817) 200-1102 or samuel.graves@nrc.gov.
Sincerely,/RA/
Gregory E. Werner, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 50-498 and 50-499 License Nos. NPF-76 and NPF-80
Enclosure:
Triennial Fire Protection Inspection Documentation Request
cc w/encl: Electronic Distribution