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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. 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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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P.O. BOX 3100 NIAMI, FLORIDA 33I01 FLORIDA POWER SI LIGHT COMPANY April 18, 1977 L-77-116 Mr. Ernst Volgenau, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Volgenau:
Re: St. Lucie Unit 1 Docket No. 50-335 RWT Overflow The attached report is being submitted in accordance with 10 CFR 20.405(a)(5). At the time of the event, a telephone report. was made to the Region II Office of Inspection and Enforcement in accordance with Regulatory Guide 1.16, section C.4.
Very truly yours, Robert E. Uhrig Vice President REU/MAS/ms Attachment.
cc: Norman C. Moseley, Region II Robert Lowenstein, Esquire HELPING BUILD FLORIDA
ATTACHMENT Re: St. Lucie Unit 1 Docket No. 50-335 RWT Overflow On April 6, 1977, during a unit outage, the refueling water tank was overfilled. The cverflow from the RWZ entered the storm drain system which drains to the east storm water basin. This basin is within the site boundary but outside the'adiation Controlled Area.
The incident occurred while operations was lowering the RCS level in pre-paration for repairing a steam generator manway gasket. Upon noticing the RWT overflowing, immediate action was to stop all flow into the tank.
After a short valve alignment the level in the RHT was lowered by pumping some of the tank's contents back into the RCS. Approximately 3,800 gallons were estimated to have overflowed. Of this, approximately 2,850 gallons was calculated to have reached the storm water basin.
- g. ~Ana1 sis:
Although the activity has been released from the Radiation Controlled Area, it has been retained within the site boundaries since the storm sewers discharge to the on-site storm water basin. (See attached sketch)
Immediate implementation of radiological controls, in the areas of concern, prevented contamination from being spread beyond the initially affected areas. No significant radiation exposure problems have occurred due to this incident.
I C. Evaluation Extent and Ha nitude:
(1) Samples of the overflow during the incident were analyzed for Gamma Isotopic Activity, Gross Alpha, Tritium and Strontium. (See Table I)
(2) Samples of the East Storm Basin from four different locations were analyzed individually showing good mixing and composited for low level counting of Gamma Isotopic Activity, Tritium and Strontium.
'See Table II)
(3) Calculations based on Tritium have shown the actual quantity of the release to the storm drain to he 2 g56 gallons.
(a) Total activity discharged from the controlled area 3e 27 curies (b) Total activity in the basin water based on C (2) above 1.61 curies (c) Total. activity remaining in storm sewer piping, basin mud and vege-tation ~ 1-66 curies
REFUELING WATER TANK 0 LOW APRIL 6, 1977 Page Two C. Evaluation Extent and Ma nitude, Continued (4) Results from item C (2) above have shown all isotopes in the East Storm Water Basin to be less than their respective MPC's with the following exceptions:
Conc MPC Iodine 131 2.4 X 10 3 X 10 7
- Iodine 133 has a half-life of 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> and should decay to below its MPC in approximately 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> from time of sample (4/6/77 9 1830).
(5) Samples taken from the West Storm Basin (approximately 500 feet west of the affected Storm Basin) on 4/7/77, approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the release showed no detectable activity. (See Table III)
(6) Additional surveillance of. the Basin and surrounding areas is con-tinuing at this time (canals, Atlantic Ocean, Indian River).
.D. Cause:
Although there were some mitigating circumstances (which will be evaluated as part of the corrective. actions), the root cause was the Operator not responding to the high RWT level and not reducing the level to clear the annunciator.
E. Corrective Action:
~
The affected areas were roped off, posted, surveyed and sampled. The around the RWT will be removed and properly disposed of. The manholes fill will be cleaned and the drain lines flushed. All of these efforts will be closely followed by the Health Physics Department.
At the present time the final plans for disposition of the water in the Storm Water Basin are not completed.
The FRG has requested that Power Plant Engineering review the piping for the RMT overflow and provide alternatives if they are deemed'ecessary, The operating procedures which involve adding water to the RWT have been revised to address assurances that adequate volume is available in the tank and that filling of the tank is secured upon receipt of a high level alarm.
0 E
FLORI D~OVER 8 LI GHT COMPANY 4
PFe LUCI E UNIT I 1 RADI OACTI VE ANALYSIS REPORT 1~ DATE/TIME 2o SAMPLE LOCATION 3e SAMPLE TYPE CP e 4o TRI TI tM ( UC I /ML) 5o STRONTI U.'4 (UCI/HL)
'o 'GROSS ALPHA (UCI/ML)
Vo REMARKSA g o e
S GAMMA SPECTRUM ANALYSIS! CALL VALUES I N UCI/ML)
MN 54 l CO-58 FE" 59 CO-60 SB-122 SB-124 BR-82 I"131 I"'133 NB-95 MO 99 CS" 136 CS 137
'R" TC 99M 95
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I FLORI D ONER 8 LI GHT COMPANY ST>> 1 UCI E UNIT i'1 RADI OACTI VE ANALYSIS REPORT I DATE/TIME 3'.
2>> SAMPLE LOCATION ~p' P g gl 3>> SAMPL E TYP E 4>> TRI TI t'ai (UCI /ML) 5>> STRONTI U'0 ( UCI/HL) 6>> 'GROSS ALPHA (UCI/ML) 7>> REMARKSQ re Zi> Qs 8>> GAMMA SPECTRUM ANA1 YSIS! (ALL VALUES IN UCI/ML>
MN 54 ~-F CO-58 W/
'O" FE" 59 0 60 SB- i 22 SB- 124
'I R" 82 e"~
l3l I-l33
~ HB-9 5 MO-99 CS" 1 36 CS-137 TC-99M Q ~
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v FLORIDA POPER 4 LI GHT COMPANY v
LUCI E UNIT PI RADIOA TI VE ANALYSIS REPORT Io DATE/TIME 2o SAMPL E LO GATI ON 3o SAMPL E TYP E 4o TRI TI Ui'I ( UCI /ML)
So STRONTI Us<I ( UCI /HL) 6+= 'GROSS ALPHA (UCI/ML) 7o REMARKS A AS~' g C <~P J'8loed Si FE 59
'SB 222 GAMMA SPECTRUM pg zP
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ANALYSIS:
co-ss CO- 60 SB-124
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(ALL VALUES I N UCI/ML)
J, BR-82
- I"131 NB-9 5 4 'P'-233 MO 99 CS" 136 CS" 237 TC-99M 'R" 95
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