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Category:Letter
MONTHYEARCP-202400424, (Cpnpp), Core Operating Limits Report (Colr), Unit 2 Cycle 22, (ERX-24-001, Revision 0)2024-11-0404 November 2024 (Cpnpp), Core Operating Limits Report (Colr), Unit 2 Cycle 22, (ERX-24-001, Revision 0) IR 05000445/20240032024-10-30030 October 2024 Integrated Inspection Report 05000445/2024003 and 05000446/2024003 IR 05000445/20244042024-10-23023 October 2024 Security Baseline Inspection Report 05000445/2024404 and 05000446/2024404 (Public) IR 07200074/20244012024-10-10010 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200074/2024401 Public 05000445/LER-2024-002-01, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-10-0303 October 2024 Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions 05000446/LER-2024-001-01, Unit Two, Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-09-30030 September 2024 Unit Two, Recurring Reactor Scrams Associated with Main Feedwater System Modifications CP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel2024-09-12012 September 2024 License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel ML24031A6322024-09-11011 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4), Final Safety Analysis Report Update Schedule (EPID L-2023-LLE-0023) - Letter ML24243A0152024-09-0303 September 2024 – Notification of Comprehensive Engineering Team Inspection (05000445/2025012 and 05000446/2025012) and Request for Information ML24194A1332024-08-28028 August 2024 Issuance of Amendment Nos. 190 and 190, Respectively, Revision to Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown ML24228A2252024-08-22022 August 2024 Relief to Use Later Code Edition for Inservice Inspection Program ML24179A0772024-08-20020 August 2024 Issuance of Amendment Nos. 189 and 189, Respectively, Extension of Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24232A2412024-08-19019 August 2024 Information Request, ISFSI Security IR 2024401 ML24232A2262024-08-19019 August 2024 Information Request, Security IR 2024404 IR 05000445/20240052024-08-15015 August 2024 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2024005 and 05000446/2024005) CP-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202400319, (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-13013 August 2024 (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality ML24177A2692024-08-0707 August 2024 Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024 (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality IR 05000445/20240022024-07-31031 July 2024 Units 1 and 2 - Integrated Inspection Report 05000445/2024002 and 05000446/2024002,and Independent Spent Fuel Storage Installation Inspection Report 07200074/2024001 IR 05000445/20244032024-07-16016 July 2024 Security Baseline Inspection Report 05000445/2024403 and 05000446/2024403 (Full Report) ML24187A0372024-07-15015 July 2024 Withdrawal of Requested Licensing Action Exemption from Select Requirements of 10 CFR Part 55, Operators Licenses ML24192A1862024-07-10010 July 2024 Notification of Inspection (NRC Inspection Report 05000445/2024003 and 05000446/2024003) and Request for Information ML24185A1382024-07-0202 July 2024 Inservice Inspection Request for Information IR 05000445/20244012024-06-26026 June 2024 MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024 (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5 CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024 (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0 IR 05000445/20240122024-06-17017 June 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000445/2024012 and 05000446/2024012 ML24120A3632024-06-10010 June 2024 Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants 05000445/LER-1924-002, (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-06-0303 June 2024 (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024 (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024 (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator 05000446/LER-2024-001, (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-05-13013 May 2024 (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications 05000445/LER-2024-001, Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning2024-05-0606 May 2024 Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A3062024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yahola, s, Kialegee Tribal Town ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A2922024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A3042024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe ML24120A2942024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation ML24120A2962024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Kaskaske, D, Kickapoo Tribe of Oklahoma ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation 2024-09-30
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Text
ber 8, 2016
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 - NRC SECURITY INSPECTION REPORT 05000445/2016201 AND 05000446/2016201 PRELIMINARY GREATER THAN GREEN FINDING
Dear Mr. Peters,
On November 8, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your Comanche Peak Nuclear Power Plant, Units 1 and 2. On November 8, 2016, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
Section 3.2.b of the enclosed report documents a finding with an associated apparent violation that the NRC has preliminarily determined to have greater than very low security significance.
We assessed the significance of each finding using the Physical Protection Significance Determination Process (SDP) and readily available information. The deficiencies associated with the finding were promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspectors left the area.
We are considering escalated enforcement for the apparent violation consistent with our Enforcement Policy, which can be found at http://www.nrc.gov/about-nrc/regulatory/
enforcement/enforce-pol.html. Because the NRC has not made a final determination in this matter, no Notice of Violation is being issued at this time. In addition, please be advised that the number and characterization of the apparent violation described in the enclosed inspection report may change as a result of further NRC review. We intend to issue our final significance determination and enforcement decision, in writing, within 90 days from the date of this letter. The NRCs significance determination process (SDP)
is designed to encourage an open dialogue between your staff and the NRC; however, neither the dialogue nor the written information you provide should affect the timeliness of our final determination.
Before we make a final decision on this matter, we are providing you with an opportunity to (1) attend a regulatory conference where you can present to the NRC your perspective on the facts and assumptions the NRC used to arrive at the finding and assess its significance, or (2) submit your position on the finding to the NRC in writing.
If you request a regulatory conference, it should be held within 40 days of your receipt of this letter and we encourage you to submit supporting documentation at least 10 days prior to the conference in an effort to make the conference more efficient and effective. The focus of the regulatory conference is to discuss the significance of the finding and not necessarily the root cause(s) or corrective action(s) associated with the finding. If you choose to attend a regulatory conference, it will be closed to public observation since Security-Related Information will be discussed. If you decide to submit only a written response, it should be sent to the NRC within 40 days of your receipt of this letter. If you decline to request a regulatory conference or to submit a written response, you relinquish your right to appeal the final SDP determination, in that by not doing either, you fail to meet the appeal requirements stated in the Prerequisite and Limitation sections of Attachment 2 of the NRC Inspection Manual Chapter 0609.
If you choose to send a response, it should be clearly marked as a Response to an Apparent Violation; (EA-16-143) and should include for the apparent violation: (1) the reason for the apparent violation or, if contested, the basis for disputing the apparent violation; (2) the corrective steps that have been taken and the results achieved; (3) the corrective steps that will be taken; and (4) the date when full compliance will be achieved. Your response may reference or include previously docketed correspondence, if the correspondence adequately addresses the required response.
Additionally, your response should be sent to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV, 1600 E. Lamar Blvd, Arlington, Texas 76011; the Director, Office of Enforcement, Washington, DC 20555-0001; the Director, Office of Nuclear Security and Incident Response, Washington, DC 20555-0001; and the NRC resident inspector at the Comanche Peak Nuclear Power Plant, Units 1 and 2. If an adequate response is not received within the time specified or an extension of time has not been granted by the NRC, the NRC will proceed with its enforcement decision or schedule a Regulatory Conference. Please contact Mr. Robert C. Johnson, Chief, Security Performance Evaluations Branch at 301-287-3688, and in writing, within 7 days from the issue date of this letter to notify the NRC of your intentions. If we have not heard from you within 7 days, we will continue with our significance determination and enforcement decision.
The NRC inspectors also documented one finding of very low security significance (Green) in the enclosed report. This finding involved a violation of NRC requirements. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV, 1600 E. Lamar Blvd, Arlington, Texas 76011; the Director, Office of Enforcement, Washington, DC 20555-0001; the Director, Office of Nuclear Security and Incident Response, Washington, DC 20555-0001; and the NRC resident inspector at the Comanche Peak Nuclear Power Plant, Units 1 and 2.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs Rules of Practice and Procedure, a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room and in the NRCs Agencywide Documents Access and Management System, accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. However, the enclosed report contains Safeguards Information as defined by 10 CFR 73.21, Protection of Safeguards Information: Performance Requirements, and its disclosure to unauthorized individuals is prohibited by Section 147 of the Atomic Energy Act of 1954, as amended. Therefore, the material in the enclosed report will not be made publically available. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. If Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii) the NRC is waiving the affidavit requirements of your response.
Sincerely,
/RA D. Pretzello Acting for/
Michael C. Layton, Director Division of Security Operations Office of Nuclear Security and Incident Response Dockets: 50-445, 50-446 Licenses: NPF-87, NPF-89 Nonpublic Enclosure:
Inspection Report 05000445/2016201 and 05000446/2016201 w/Attachment: Supplemental Information cc w/enclosure: M. McNally, TEX Operations Company LLC MLML16315A045 Entire Report: Non-Sensitive Publicly Available Keyword:
SUNSI Review CompleteBy: Sensitive Non-Publicly Available MD 3.4 Non-Public A.3 Cover Letter Only: Non-Sensitive Publicly Available Keyword:
SUNSI Review CompleteBy: Sensitive Non-Publicly Available SUNSI Review Complete OFFICE NSIR/DSO NSIR/DSO NSIR/DSO Region IV NSIR/DSO/SPEB NSIR/DSO NAME T. Barry J. Berry J. Clark M. Haire R. Johnson D. Pretzello for/M. Layton DATE 11/1/2016 11/3/2016 11/15/2016 11/28/2016 12/08/16 12/08/2016