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Category:Inspection Report
MONTHYEARIR 05000335/20240052024-08-22022 August 2024 Updated Inspection Plan for St. Lucie, Units 1 & 2 - Report 05000335/2024005 and 05000389/2024005 IR 05000335/20240022024-08-13013 August 2024 Integrated Inspection Report 05000335-2024002 and 05000389-2024002 IR 05000335/20244012024-06-0303 June 2024 Security Baseline Inspection Report 05000335/2024401 and 05000389/2024401 IR 05000335/20240012024-05-10010 May 2024 Integrated Inspection Report 05000335/2024001 and 05000389/2024001 IR 05000335/20230062024-02-28028 February 2024 Annual Assessment Letter for St Lucie Units 1 & 2 - Report 05000335/2023006 and 05000389/2023006 IR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 IR 05000335/20230042024-01-24024 January 2024 – Integrated Inspection Report 05000335/2023004 and 05000389/2023004 IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 IR 05000335/20234202023-03-21021 March 2023 Security Baseline Inspection Report 05000335/2023420 and 05000389/2023420 IR 05000335/20220062023-03-0101 March 2023 Annual Assessment Letter for St. Lucie Units 1 & 2 (Report 05000335/2022006 and 05000389/2022006) IR 05000335/20220042023-02-10010 February 2023 Integrated Inspection Report 05000335/2022004 and 05000389/2022004 IR 05000335/20220112022-12-27027 December 2022 Triennial Fire Protection Inspection Report 05000335/2022011 and 05000389/2022011 IR 05000335/20220032022-11-0404 November 2022 Integrated Inspection Report 05000335/2022003 and 05000389/2022003 ML22208A1762022-08-0404 August 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report IR 05000335/20220022022-08-0101 August 2022 Integrated Inspection Report 05000335/2022002 and 05000389/2022002 ML22210A0782022-07-22022 July 2022 Stl 2022003 Document Request IR 05000335/20220122022-06-29029 June 2022 Biennial Problem Identification and Resolution Inspection Report 05000335 2022012 and 05000389 2022012 IR 05000335/20224012022-05-20020 May 2022 Security Baseline Inspection Report 05000335/2022401 and 05000389/2022401 IR 05000335/20220012022-05-12012 May 2022 Integrated Inspection Report 05000335/2022001 and 05000389/2022001 IR 05000335/20220102022-04-27027 April 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000335/2022010 and 05000389/2022010 IR 05000335/20214022022-04-0404 April 2022 Material Control and Accounting Program Inspection Report 05000335/2021402 and 05000389/2021402 - Public IR 05000335/20210062022-03-0202 March 2022 Annual Assessment Letter for St. Lucie, Units 1 & 2 (Report No. 05000335/2021006 and 05000389/2021006) IR 05000335/20210042022-02-14014 February 2022 Integrated Inspection Report 05000335/2021004 and 05000389/2021004 IR 05000335/20214032021-12-14014 December 2021 Security Baseline Inspection Report 05000335/2021403 and 05000389/2021403 IR 05000335/20210102021-12-0707 December 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000335/2021010 and 05000389/2021010 IR 05000335/20210032021-11-0303 November 2021 Integrated Inspection Report 05000335/2021003 and 05000389/2021003 IR 05000335/20210052021-08-25025 August 2021 Updated Inspection Plan for St. Lucie Plant Units 1 & 2 (Report 05000335/2021005 and 05000389/2021005) IR 05000335/20210022021-08-10010 August 2021 Integrated Inspection Report 05000335/2021002 and 05000389/2021002 IR 05000335/20214012021-06-23023 June 2021 Security Baseline Inspection Report 05000335/2021401 and 05000389/2021401 IR 05000335/20213012021-06-21021 June 2021 NRC Examination Report 05000335/2021301 and 05000389/2021301 IR 05000335/20210012021-05-12012 May 2021 Integrated Inspection Report 05000335/2021001 and 05000389/2021001 IR 05000335/20200062021-03-0303 March 2021 Annual Assessment Letter for St. Lucie Nuclear Plant, Unit 1 and Unit 2 Report 05000335/2020006 and 05000389/2020006 IR 05000335/20203012021-02-16016 February 2021 NRC Operator License Examination Report 05000335/2020301 and 05000389/2020301 IR 05000335/20200042021-02-0808 February 2021 Integrated Inspection Report 05000335/2020004 and 05000389/2020004 and Independent Spent Fuel Storage Installation (ISFSI) Inspection 07200061/2020002 IR 05000335/20204012021-01-0505 January 2021 Security Baseline Inspection Report 05000335/2020401 and 05000389/2020401 IR 05000335/20200112020-12-16016 December 2020 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000335/2020011 and 05000389/2020011 IR 05000335/20200032020-10-30030 October 2020 Integrated Inspection Report 05000335/2020003 and 05000389/2020003 ML20296A3732020-10-22022 October 2020 Security Inspection Report IR 05000335/20200052020-08-24024 August 2020 Updated Inspection Plan for St. Lucie Plant, Unit 1 and 2 (Report 05000335/2020005 and 05000389/2020005) IR 05000335/20200022020-07-29029 July 2020 St.Lucie Units 1 & 2 Integrated Inspection Report 05000335/2020002, 05000389/2020002, and Independent Spent Fuel Storage Installation Inspection (Lsfsi) 07200061/2020001 IR 05000335/20200102020-07-16016 July 2020 Biennial Problem Identification and Resolution Inspection Report 05000335/2020010 and 05000389/2020010 IR 05000335/20200012020-05-0505 May 2020 Integrated Inspection Report 05000335/2020001 and 05000389/2020001 and Exercise of Enforcement Discretion IR 05000335/20190062020-03-0303 March 2020 Annual Assessment Letter for St. Lucie Nuclear Plant, Units 1 and 2 NRC Report 05000335/2019006 and 05000389/2019006 IR 05000335/20190032019-11-14014 November 2019 Integrated Inspection Report 05000335/2019003 and 05000389/2019003 2024-08-22
[Table view] Category:Letter type:L
MONTHYEARL-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis 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 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-2024-125, 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 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-2024-114, 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-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review 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 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-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation 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-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-064, 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-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, 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 to 20 Years2024-01-18018 January 2024 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 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) 2024-08-07
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'jg FLORIDA POWER & LIGHT COMPANY December 8, 1977 L-77-365 Mr. James P. O'Reilly, Director, Region Office of Inspection and Enforcement II U.S. Nuclear Regulatory Commission 230 Peachtree Street, N.W., Suite 1217 Atlanta, GA 30303
Dear Mr. O'Reilly:
Re: RII:MVS 50-335/77-18 Florida Power 6 Light Company has reviewed the subject inspection report. There is no proprietary information in the report.
Very truly yours, M
Robert E. Uhrig Vice President REU/MAS/lah cc: Robert Lowenstein, Esquire
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~0+s NUCLEAR REGULATORY COMMISSION REG ION Il C O 230 PEACHTREE STREET. N.W. SUITE 1217 0 . ATLANTA,GEORGIA 30303 g . c
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<<aa>>" NOY 2 9 1977 In Reply Refer To:
RII1MVS 50-335/77-18 Florida Power and Light Company Attn: Dr. R. E. Uhrig, Vice President of Nuclear and General Engineering P. 0. Box 013100 9250 Vest Flagler Street Miami, Florida 33101 Gentlemen:
This refers to the special inspection conducted by Mr. M. V. Sinkule of t this office on November 9-10, 1977, of activities authorized by NRC Operating License No. DPR-67 for the St. Lucie facility, involving the possible contamination and(or radiation exposure of an Florida Power and Light Company employee who was in the Community Hospital of the Palm Beaches at Vest Palm Beach, Florida. The findings of this inspectioa were discussed with Mr. K. N. Harris by telephone on November 16, 1977.
Areas examined during the inspection and our findings are discussed in the attached inspection report. Vithin these areas, the inspection consisted of interviews with personnel, and observations by the inspector.
Vithin the scope of this inspection, no items of noncompliance were disclosed.
In accordance with Section 2.790 of the NRC's "Rules of Practice",
Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. If this report contains any information that you (or your contractor) believe to be proprietary, it is necessary that you make a written application within 20 days to this office to withhold such information from public disclosure. Any such application must include a full statement of the reasons on the basis of which it is claimed that the information is proprietary, and should be prepared so that proprietary information identified in the application is contained in a separate part of the document. If we do not hear from you in this t regard within the specified period, the report will be placed in the Public Document Room.
Florida Power and Light Company Should you have any questions concerning this letter, we will be glad to discuss them with you.
Sincerely, F. J. Long, Chief Reactor Operations and Nuclear Support Branch
Enclosure:
RII Inspection Report No. 50-335/77-18 cc: Mr. K. N. Harris, Plant Manager St. Lucie Plant P. 0. Box 128 Ft. Pierce, Florida 33450 Mr. Nat Weems, Assistant QA Manager P. 0. Box 128 Ft. Pierce, Florida 33450
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REGION II 230 PEACHTREE STREET, N.W. SUITE 1217 ATLANTA,GEORGIA 30303
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Report No.: 50-335/77-18 Docket No.: 50-335 License No.: DPR-67 Category: C Licensee: Florida Power and Light Company P. O. Box 013100 Miami, Florida 33101 Facility Name: St. Lucie 1 Inspection at: Community Hospital of the Palm Beaches, West Palm Beach, Florida e Inspection conducted:
Inspector: M.
November 9-10, 1977 V. Sinkule Reviewed by: CAID il -H-1 7 R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Ins ection Summar Ins ection on November 9-10 1977 (Re ort No. 50-335/77-18) alleged contamination and/or radiation exposure of a St. Lucie employee at the Community Hospital of the Palm Beaches at West Palm Beach, Florida.
The inspection involved 5 inspector-hours at the hospital by one NRC inspector.
Results: Of the area inspected, no items of noncompliance or deviations were found.
RII Rpt. No. 50-335/77-18 DETAILS I Prepared by:
M.~ V.~ Sinkule, Reactor Inspector Date Reactor Progects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: November 9-10, 1977 Reviewed by: Z-C. r~rz8~
R. C. Lewis, Chief Date Reactor Projects Section No.'2 Reactor Operations and Nuclear Support Branch
- 1. Persons Contacted J. Cogswell, Civil Defense Health Physicist H. Buchanan, FP&L Health Physics Supervisor St. Lucie H. Mercer, FP&L, Plant Coordinator C. Wells, FP&L, Operations Supervisor Dr. Serafini, Radiation Emergency Evaluation Facility Dr. Kenny, Radiation Emergency Evaluation Facility C. G. Weird, Hospital Administrator, Community Hospitaf Dr. Kiner, Attending Physician, Community Hospital K. Harris, FP&L Plant Manager St. Lucie (by telephone oa November 9, 1977)
- 2. Licensee Action on Previous Ins ection Findin s Not inspected.
- 3. Unresolved Items No new unresolved items were identified.
- 4. Fxit Interview The scope and findings of this inspection were discussed with Mr. K. N. Harris, Plant Manager, by telephone on November 16, 1977.
- 5. ~Summat of Event The inspector was contacted by the Region II office in Atlanta, Georgia, at the Turkey Point site at approximately 5:30 p.m. on November 9, 1977, and directed to proceed to the Community Hospital of the Palm Beaches where a Florida Power and Light (FP&L) employee was alleged to be contaminated and/or irradiated. The inspector was to determine if the event was associated with control of contamination or irradiation at the St. Lucie site. FP&L personnel had contacted Region II at approximately 4:30 p.m. on November 9, 1977, and described the situation.
RII Rpt. No. 50-335/77-18 E-2 The inspector arrived at the hospital at approximately 9:30 p.m. on November 9, 1977. Upon entry into the hospital the inspector submitted to a brief interview from a reporter for the Miami Herald Newspaper.
When the inspector arrived at the hospital, he conducted an interview with Community Hospital officials, FPSL plant personnel, Radiation Emergency Evaluation officials, and a representative from the County Civil Defense office. The personnel present had conducted radiation surveys and reviewed hospital records of the individual involved and had concluded that the radiation levels were due to a prescribed diagnostic intake of radioactive technesium-99, prescribed by a physician and administered at the hospital.
The Civil Defense official stated that he had been contacted by Hospital officials on November 9, 1977, after they became alarmed with the radiation levels of an individual who had been admitted to the hospital to undergo treatment for a gastrointestinal disorder and high fever on November 5, 1977. The inspector was informed that the survey taken by the Civil Defense official ranged from 10 to 50 mrem per hour on different parts of the patients body. The Civil Defense official stated that he ordered the man isolated and scrubbed. He subsequently contacted FP&L personnel who responded to the scene.
FP&L personnel stated that they had arrived on the scene at approximately 6:00 p.m. on November 9, 1977, but were not permitted to conduct surveys until approximately 7:00 p.m. The survey, which was conducted with RM-14 radiation monitors, showed that there was no contamination on the patient's skin, clothing, or in his room; however, direct radiation readings indicated the presence of radioactivity inside of his body.
FP&L personnel also stated that a radiation survey of the patient's home, personal effects, and family did not reveal the presence of radioactive contamination.
The personnel from the Radiation Emergency Evaluation Facility (REEF) in Miami arrived at the hospital and conducted an independent radiation survey and their readings agreed with those taken by FP&L personnel. They reviewed the medical records of the patient and found that the patient had been given 10 millicuries of technesium-99 on the evening of November 8, to aid in the diagnosis of the patient.
REEF personnel concluded that the technesium-99 was the source of the radiation and that this incident was not related to a radioactive source that had originated at the St. Lucie site.
RII Rpt. No. 50-335/77-18 I-3 Further discussions w1th the Civil Defense official indicated that the instrument used by him to conduct his survey was not rel1able in the low radiation ranges. It appeared to the inspector that all parties were in agreement that the radiation readings of the patient were due to the diagnostic intake, which had been prescribed by a physician.
REEF officials stated that they had taken smears of the patient and the room which did not show evidence of contamination; however, the smears would be recounted on stationary equipment at the REEF at Miami. REEF representatives also stated that the patient would be transferred to REEF on November 10, for the conduct1on of confirmatory tests.
The 1nspector revisited the hospital on the morning of November 10, and conducted an interview with the patients'octor and the hospital administrator to confirm the amount of the diagnostic intake and to determine additional circumstances surround1ng the event. The patients'octor had ordered the diagnostic intake of technes1um-99 which was administered on November 8 and also ordered gieger counter readings to be taken when he was informed, by the patient, that he was employed at a nuclear power plant and had been 1nvolved in radiation type work. The doctor also stated that he wa's concerned with the slow recovery of the patient. The inspector could not determ1ne why the hosp1tal off1cials became alarmed at the radiation levels of the patient unless the hospital personnel making the radiation survey were not aware of the diagnostic 1ntake. Dur1ng th1s interview, the inspector was informed that hospital officials had contacted REEF on November 10 and were informed that the results of a blood sampl'e taken from patient on November 9 indicated only the presence of technesium-99.
On November 11 Region II contacted the director of the REEF by telephone and was informed that the results of tests conducted on the facility conclusively proved that the only source of radiation was technesium-99.