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MONTHYEARML0419706102004-07-0101 July 2004 G20040468 - Thomas Saporito Ltr. Dtd 07/01/04 & 07/04/04, Turkey Point Petition 2.206 Project stage: Other ML0423702992004-08-0202 August 2004 G20040468 - Thomas Saporito Ltr. Dtd 7/1/04 & 7/4/04, Turkey Point Petition 2.206 Transcript Project stage: Other ML0424500022004-09-0202 September 2004 G20040468 - Thomas Saporito Ltr Re. Closure Dated 07/01/04 & 07/04/04, Turkey Point 2.206 Petition Project stage: Other 2004-08-02
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Category:Letter
MONTHYEARIR 05000335/20240022024-08-13013 August 2024 Integrated Inspection Report 05000335-2024002 and 05000389-2024002 L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24172A1562024-06-27027 June 2024 Relief Request - PSL2-I5-RR-01 Proposed Alternative to Amse Code XI Code Examination Requirements - System Leakage Test of Reactor Pressure Vessel Bottom Head and Class 1 and 2 Piping in Covered Trenches L-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports IR 05000335/20244012024-06-0303 June 2024 Security Baseline Inspection Report 05000335/2024401 and 05000389/2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 ML24135A0642024-05-17017 May 2024 Correction Letter - Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation IR 05000335/20240012024-05-10010 May 2024 Integrated Inspection Report 05000335/2024001 and 05000389/2024001 IR 05000250/20240012024-05-10010 May 2024 Integrated Inspection Report 05000250/2024001 and 05000251/2024001 ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report ML24135A0942024-05-0909 May 2024 Periodic Update to the Updated Final Safety Analysis Report ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000250/20240102024-05-0101 May 2024 Design Basis Assurance Inspection Programs Inspection Report 05000250/2024010 and 05000251/2024010 and Notice of Violation L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 ML24108A0632024-04-18018 April 2024 – Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report ML24087A1982024-04-0505 April 2024 Notice of Availability of the Final Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application 2024-08-07
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September 2, 2004 Mr. Thomas Saporito National Environmental Protection Center Post Office Box 1173 Jupiter, Florida 33458
Dear Mr. Saporito:
Your petition addressed to the U.S. Nuclear Regulatory Commission (NRC) Executive Director for Operations, dated July 1, 2004, as supplemented on July 4, 2004, has been referred to the Office of Nuclear Reactor Regulation pursuant to Title 10, Code of Federal Regulations (10 CFR), Section 2.206. You requested that the NRC take immediate action to cause the cold shutdown of the Turkey Point Nuclear Power Plant, Units 3 and 4, and the Saint Lucie Plant Units 1 and 2, operated by the Florida Power and Light Company (FPL, the licensee).
Additionally, you requested immediate enforcement action against the licensee for the alleged failure to adhere to the requirements of 10 CFR 50.7, Employee Protection. The enforcement action proposed also includes a request for the issuance of a Notice of Violation and a civil penalty of $100,000 per day retroactive to June 3, 1994. The basis for your request relates to three previous employee protection cases against FPL and your assertion that the . . . licensee cannot demonstrate any amount of reasonable assurance . . . that the overall work environment at the Turkey Point and St. Lucie nuclear stations is totally free of an atmosphere which would otherwise dissuade licensee employees from raising nuclear safety concerns to the NRC or to the licensee.
The Petition Review Board (PRB) considered the information provided in your petitions as well as the information you provided during a teleconference with the PRB on August 2, 2004.
During the teleconference, you indicated a revision to your request to impose a civil penalty against FPL. The revision would increase your proposed civil penalty from $100,000 to
$120,000 per day retroactive to June 3, 1994. Based on the information provided by you and the records of the NRC staffs activities in this area, the PRB considered your petition as well as your supplemental letter. The PRB determined that there was no need for action to immediately shut down Turkey Point Units 3 and 4 or Saint Lucie Units 1 and 2. A review of NRC activities revealed that you have previously raised these same issues to the NRC staff under the 10 CFR 2.206 Petition process in a letter dated April 23, 1997, as supplemented on May 11 and May 17, 1997. The Directors Decision (DD) 97-20 denying your petition was issued in a letter to you dated September 8, 1997.
The issues you raised in this petition request were previously reviewed by the NRC Office of Investigations (OI) and documented in Report of Investigation (ROI) 2-1988-012. After investigating your claims of retaliation, OI was unable to substantiate that individuals were terminated as a result of protected activity. OI also reviewed the work environment and concluded that a chilled environment did not exist. Additionally, as a result of allegations made to the NRC, a team inspection was conducted at FPLs Turkey Point Nuclear Power Plant from October 28 to November 8, 1991, to determine if personnel practices resulted in a chilling effect with regard to pursuing a safety issue.
T. Saporito In the associated NRC Inspection Report 50-250(251)/91-45, the NRC staff indicated that
[t]here was no evidence found to substantiate the allegations of an overall atmosphere of intimidation, threats, coercion, harassment, or negative evaluations to limit the pursuit of safety issues.
In accordance with NRC Management Directive 8.11, Review Process for 10 CFR 2.206 Petitions, the staff will not review a petition if the petition raises issues that have already been the subject of NRC staff review and evaluation either on that facility, other similar facilities, or on a generic basis, for which a resolution has been achieved, the issues have been resolved, and the resolution is applicable to the facility in question. This would include requests to reconsider or reopen a previous enforcement action, unless significant new information was presented. As these issues have been previously reviewed and no significant new information was provided, the PRB has concluded that your petition does not meet the criteria for consideration under 10 CFR 2.206. This concludes the NRC staffs effort on this petition request.
Thank you for bringing these issues to the attention of the NRC.
Sincerely,
/RA James E. Lyons for/
Ledyard B. Marsh, Director Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-250, 50-251, 50-335, and 50-389
Enclosure:
NEPC 2.206 Request
ML042450002 NRR-106 OFFICE PDII-2/PM PDII-2/PM PDII-2/LA PDII-2/SC(A) DLPM/PD DLPM/PD DLPM/D NAME EBrown BMoroney BClayton MMarshall EHackett HBerkow JLyons for LMarsh DATE 08/30/04 08/30/04 08/30/04 08/30/04 08/30/04 08/31/04 09/02/04