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| {{#Wiki_filter:U.S.NUCL.EAR REGULATORY COMMi~lON DISTRIBUTION AFT'SSUANCE 0 PERATING LICENSE NRC ARM$195 (Z-7B)'RC DISTRIBUTION FDR PART 50 DOCKET MATERIAL DOCKET NUMBER t5-FILE NUMBER TO Mr.Victor Stello FROM: Florida Power&Light Company Miami, Florida@Robert ED Uhrig DATE OF DOCUMENT 12/21/77 OATS RE CEI V E 0 12/27/77~LLUTTER~ORIGINAL CJCOPY DESCRIPTION CINOTORIZEO | | {{#Wiki_filter:DISTRIBUTION AFT'SSUANCE 0 PERATING LICENSE NRC ARM $195 U.S. NUCL.EAR REGULATORY COMMi~lON DOCKET NUMBER (Z-7B) t5- |
| ~UN C LASS I F I E 0 PROP INPUT FORM ENCL OSURE NUMBER OF COPIFS RECEIVED License No.DPR-67 Appl for Amend: tech specs proposed change concerning high radiation area monitoring. | | 'RC DISTRIBUTION FDR PART 50 DOCKET MATERIAL FILE NUMBER TO FROM: DATE OF DOCUMENT Florida Power & Light Company 12/21/77 Mr. Victor Stello Miami, Florida@ OATS RE CEI V E0 Robert ED Uhrig 12/27/77 |
| ~~inotorized 12/21/77~~~~.(1-P)(1-P)+(3-P) | | ~LLUTTER CINOTORIZEO PROP INPUT FORM NUMBER OF COPIFS RECEIVED |
| PLANT NAME: St.Lucie Unit No.1'RJL 12/28/77 SAFETY BRANCH CHIEF: 7 FOR ACTION/INFORMATION REG F INTERNAL 0 Rl BUTION IST I3'.MCGOU PDR: flIC SIC PCRS 1 CYS SEiIT CATEGP EXTERNAL OISTRIBUTION CONTROL NUMBER 7734soo69 I J 4 C ( | | ~ORIGINAL CJCOPY |
| P.O.BOX 013100, MIAMI, FL 33101 yVll/g e=FLORIDA PGWER&LIGHT COMPANY December 21, 1977 L-77-388 Director of Nuclear Reactor Regulation Attention:
| | ~ UN C LASS I F I E 0 DESCRIPTION ENCL OSURE License No. DPR-67 Appl for Amend: tech specs proposed change concerning high radiation area monitoring. ~ ~ inotorized 12/21/77 ~ ~ ~ ~ . |
| Mr.Victor Stello, Director Division of Operating Reactors U.S.Nuclear Regulatory Commission Washington, D.C.20555<<$!+lpgpgl<<//'L,+<<'///<<(, (<</I
| | (1-P) (1-P)+(3-P) |
| | PLANT NAME: St. Lucie Unit No. 1 |
| | 'RJL 12/28/77 SAFETY FOR ACTION/INFORMATION BRANCH CHIEF: 7 INTERNAL 0 IST Rl BUTION REG F I3'. MCGOU EXTERNAL OISTRIBUTION CONTROL NUMBER PDR: |
| | flIC SIC PCRS 1 CYS SEiIT CATEGP 7734soo69 |
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| ==Dear Mr.Stello.:== | | I J |
| Re: St.Lucie Unit 1 Docket No.50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 In accordance with 10 CFR 50.30, Florida Power 6 Light Company submits herewith three (3)signed originals and forty (40)copies of a request, to amend Appendix A of Facility Operating License DPR-67.The proposed amendment is described below and shown on the accompanying Technical Specification pages bearing the date of this letter in the lower'xight hand coxner.Specification 6.13 (High Radiation Area)is replaced with the corresponding section from the Standard Technical Specifications. | | 4 C |
| The proposed amendment has been reviewed by the St.Lucie Facility Review Group and the Florida Power a Light Company Nuclear Review Board.They have concluded that it: does not.involve an unreviewed | | ( |
| 'safety question.A written safety evaluation is attached.Very truly yours, Robert Z.Uhrig Vice President REU/MAS/cpc Attachment cc: Mr.James P.O'Reilly, Region II Robert Lowenstein, Esquire Edward Reeves'~g800 06'9 PEOPLE...SERVING PEOPLE ADMINISTRATIVE CONT'I Unless otherwise authorized by the Commission, the licensee shall not assign protection factors in excess of those specified. | | |
| | P.O. BOX 013100, MIAMI, FL 33101 yVll/g e= |
| | FLORIDA PGWER & LIGHT COMPANY December 21, 1977 L-77-388 Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director <<$ !+ lpgpgl<<// 'L,+<< |
| | Division of Operating Reactors '// |
| | U. S. Nuclear Regulatory Commission /<< |
| | (, (<< /I Washington, D. C. 20555 |
| | |
| | ==Dear Mr. Stello.:== |
| | |
| | Re: St. Lucie Unit 1 Docket No. 50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 In accordance with 10 CFR 50.30, Florida Power 6 Light Company submits herewith three (3) signed originals and forty (40) copies of a request, to amend Appendix A of Facility Operating License DPR-67. |
| | The proposed amendment is described below and shown on the accompanying Technical Specification pages bearing the date of this letter in the lower'xight hand coxner. |
| | Specification 6.13 (High Radiation Area) is replaced with the corresponding section from the Standard Technical Specifications. |
| | The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power a Light Company Nuclear Review Board. They have concluded that it: does not. involve an unreviewed |
| | 'safety question. A written safety evaluation is attached. |
| | Very truly yours, Robert Z. Uhrig Vice President REU/MAS/cpc Attachment |
| | '~g800 cc: Mr. James P. O'Reilly, Region Robert Lowenstein, Esquire Edward Reeves II 06'9 PEOPLE... SERVING PEOPLE |
| | |
| | ' |
| | ADMINISTRATIVE CONT I |
| | Unless otherwise authorized by the Commission, the licensee shall not assign protection factors in excess of those specified. |
| in Table 6.12-1 in selecting and using respiratory protective equipment. | | in Table 6.12-1 in selecting and using respiratory protective equipment. |
| REVOCATION 6.'12.3 The specifications of Section'6.12 shall be revoked in their entir ty upon adoption of'.th proposed chanq to 10 CFP.20 Section 20.103, which would make such provisions un;ecessary | | REVOCATION 6.'12.3 The specifications of Section'6.12 shall be revoked in their entir ty upon adoption of'.th proposed chanq to 10 CFP. 20 Section 20.103, which would make such provisions un;ecessary |
| '6.13 HIGH RADIATION AREA 633.1 In lieu of the"control device" or"alarm signal" required by paragraph 20.203(c){2)of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of'Radiation Vork Permit~.Any individual or group of individuals p rmitted to e..-.": such areas shall be provided, with or accoiI.panied by one or more o;:i following= | | ' |
| ~a.A radiation'monitoring device which continuously indicates the radiation dose rate'n-the area.b..A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is'eceived. | | 6.13 HIGH RADIATION AREA 633.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c) {2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of' Radiation Vork Permit~. |
| Entry into such areas with this~rronitoring device may be made.after the dose rata level in'the area has be n es ablished and personnel have been made knowl-edqeable of-them.'c.An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device..This individual shall be responsible for oroviding posiiive control over the activities within the area and shall perfom periodic radiation surveillance a the frequency specified by the facility Health Physicist in the Padiation bfork Permit 6.j-3.2 The reouirements of 6.g3.l, above, shall also aoply to each hign radiation'rea in which the intensity or radiation is greater than 1000 mrem/hr En addition, locked doors shall be provided to prevent unauthorized'ntry into such areas and the keys shall be maintained under the admin~strative contro1 of the Shift Supervisor on duty and/or the Plant H alth Physicist. | | Any individual or group of individuals p rmitted to e.. -.": such areas shall be provided, with or accoiI.panied by one or more o;:i following= |
| '~li I'.p,'I I 111-,p f h R'**q ment during the performance of their assigned radiation protection duties, provided they compIy with approved radiation protection procedur s for entry into high radiation areas.~'I ST.LUCIE-'NIT 1 6-19 3.2/23./77 SAFETY EVALUATION Re: St.Lucie Unit 1 Docket No.50-335 Hi A Radiation Area Mon~itorin Introduction This evaluation supports a proposed change to Technical Specification 6.13 on administrative control of high radiation areas.The existing Specification is replaced by the corresponding section from the Standard Technical Specifications.
| | ~ |
| Evaluation The current Specification requires that any individual or group of individuals permitted to enter a high radiation area be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.For the case of containment entry with the reactor at power, such a-requirement represents good.health physics practice.It does not, however, guarantee'he intended exposure control in all situations. | | : a. A radiation'monitoring device which continuously indicates the radiation dose rate'n-the area. |
| For example, when an individual or group of individuals enters a high radiation area which has been surveyed and posted in accordance with the stringent requirements of the Radiation Work Permit (RWP)procedure, a continuously indicating dose rate device located in the same area will not necessarily provide additional exposure control.The device must be read frequently to determine if radiological conditions have changed.The current Specification does not guarantee that an individual intent on doing his job will also remember to read the radiation monitoring device.Thus, such a device may satisfy the legal requirements of the current Specification without satisfying the intent of the Specification. | | : b. .A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is'eceived. Entry into such areas with this |
| Exposure control is achieved in part by administrative pro-cedures that require a radiation survey prior to entry into high radiation areas.Once dose rates are known, Health Physics Department personnel set"stay times" for individuals for the purpose of limiting the individual's accumulated dose.By using one of the proposed alternatives to the current Specification, i.e., the dose integrating/alarming device, we believe that better exposure control is possible.Under this alternative, an individual could have an electronic device attached to his protective clothing, or health physics personnel could set'up a dose integrating device in the area.Such devices would have an audible alarm that would annunciate when a preset accumulated dose (determined by health physics personnel) was exceeded.All individuals would be instructed to leave the work area should an alarm occur.By using a device with an audible alarm setpoint, personnel would be better protected against the effects of changes in the dose rate.With current practice, a worker cannot become aware of a change in dose rate without periodically monitoring a dose rate device.Thus, the proposed specification is con-servative with respect to the current Specification because it does not depend on individuals monitoring their pocket dosi-meters frequently (as they are instructed to do)or monitoring a separate dose rate device.We are also proposing an additional alternative to the current specification, i.e., the provision for direct health physics coverage of a job by a health physics qualified individual. | | ~ rronitoring device may be made. after the dose rata level in 'the area has be n es ablished and personnel have been made knowl-edqeable of- them. ' |
| For example, consider the case of steam generator water box entries for the purpose of tube inspection or plugging.Health physics personnel determine the dose rates in the water box, set stay times, and determine what protective clothing must be worn during the entry.Because of the high.dose rates, airborne activity, and contamination, stay times of only minutes are allowed, and a double set of coveralls, a plastic suit, and supplied air are required.During the entry, health physics personnel are at the entrance to the water box to ensure tha" the individual is properly dressed.Once the entry is made, the health physics personnel time the individual to ensure that he minimizes his exposure and does not exceed the plant's administrative exposure limits nor those of the Commission. | | : c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. |
| Because of the air line and other clothing and equipment that, the individual making the entry must carry into the confined space, and the necessity for short stay times, he cannot.carry a meter with him.We believe that in this case and similar cases, our practice is appropriate and that it is in keeping with the exposure control intent of the present Specification. | | .This individual shall be responsible for oroviding posiiive control over the activities within the area and shall perfom periodic radiation surveillance a the frequency specified by the facility Health Physicist in the Padiation bfork Permit 6.j-3.2 The reouirements of 6.g3.l, above, shall also aoply to each hign radiation'rea in which the intensity or radiation is greater than 1000 mrem/hr En addition, locked doors shall be provided to prevent unauthorized'ntry into such areas and the keys shall be maintained under the admin~strative contro1 ' of the Shift Supervisor on duty and/or the Plant H alth Physicist. |
| III.Conclusion Based on the considerations described above, (l)the proposed, change does not increase the probability or consequences o'accidents or malfunctions of equipment important to safety and does not reduce the margin of safety as defined in the basis for'ny technical specification, therefore, the change does not involve a significant hazards consideration, (2)there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3)such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety o the public. | | ~li ment I'. p, 'I I 111 -,p f h R'** |
| 0 Xl l~4 e( | | during the performance of their assigned radiation protection duties, provided they compIy with approved radiation protection q |
| STATE OF FLORIDA))COUNTY OF DADE)ss~n Robert E.Uhrig, being first duly sworn, deposes and says: That he is a Uice President of Florida Power 6 Light, Company, the Licensee herein;That he has executed the foregoing document;that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.Robert E.Uhrig Subscribed and sworn to before me this Q J~~day of 19~7 NOTARY PUBLIC, in and for the County of Dade, State of Florida NOTARY PUBLIC STATE OF FLORIDA eL LARGE MY COMMISSION EXPIRES AUGUST 24, LSSI L4'ommission expires: BGNDED'THRU LIAYNARD BGNDIMG AGENGY V~VL~~~RFf'V g g~pigq-py<<*-''-l"~Uf,ll, 8<(f>EC 27 PM l2 ts)I 1I h V ('.r~<q(e ll~e U Cq L'h}} | | procedur s for entry into high radiation areas. |
| | ~ 'I ST. LUCIE -'NIT 1 6-19 3.2/23./77 |
| | |
| | SAFETY EVALUATION Re: St. Lucie Unit 1 Docket No. 50-335 Hi A Radiation Area Mon~itorin Introduction This evaluation supports a proposed change to Technical Specification 6.13 on administrative control of high radiation areas. The existing Specification is replaced by the corresponding section from the Standard Technical Specifications. |
| | Evaluation The current Specification requires that any individual or group of individuals permitted to enter a high radiation area be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area. |
| | For the case of containment entry with the reactor at power, such a -requirement represents good .health physics practice. |
| | It does not, however, guarantee'he intended exposure control in all situations. |
| | For example, when an individual or group of individuals enters a high radiation area which has been surveyed and posted in accordance with the stringent requirements of the Radiation Work Permit (RWP) procedure, a continuously indicating dose rate device located in the same area will not necessarily provide additional exposure control. The device must be read frequently to determine changed. |
| | if radiological conditions have The current Specification does not guarantee that an individual intent on doing his job will also remember to read the radiation monitoring device. Thus, such a device may satisfy the legal requirements of the current Specification without satisfying the intent of the Specification. |
| | Exposure control is achieved in part by administrative pro-cedures that require a radiation survey prior to entry into high radiation areas. Once dose rates are known, Health Physics Department personnel set "stay times" for individuals for the purpose of limiting the individual's accumulated dose. By using one of the proposed alternatives to the current Specification, i.e., the dose integrating/alarming device, we believe that better exposure control is possible. Under this alternative, an individual could have an electronic device attached to his protective clothing, or health physics personnel could set 'up a dose integrating device in the area. |
| | Such devices would have an audible alarm that would annunciate when a preset accumulated dose (determined by health physics personnel) was exceeded. All individuals would be instructed |
| | |
| | to leave the work area should an alarm occur. |
| | By using a device with an audible alarm setpoint, personnel would be better protected against the effects of changes in the dose rate. With current practice, a worker cannot become aware of a change in dose rate without periodically monitoring a dose rate device. Thus, the proposed specification is con-servative with respect to the current Specification because does not depend on individuals monitoring their pocket dosi-it meters frequently (as they are instructed to do) or monitoring a separate dose rate device. |
| | We are also proposing an additional alternative to the current specification, i.e., the provision for direct health physics coverage of a job by a health physics qualified individual. |
| | For example, consider the case of steam generator water box entries for the purpose of tube inspection or plugging. Health physics personnel determine the dose rates in the water box, set stay times, and determine what protective clothing must be worn during the entry. Because of the high. dose rates, airborne activity, and contamination, stay times of only minutes are allowed, and a double set of coveralls, a plastic suit, and supplied air are required. During the entry, health physics personnel are at the entrance to the water box to ensure tha" the individual is properly dressed. Once the entry is made, the health physics personnel time the individual to ensure that he minimizes his exposure and does not exceed the plant's administrative exposure limits nor those of the Commission. |
| | Because of the air line and other clothing and equipment that, the individual making the entry must carry into the confined space, and the necessity for short stay times, he cannot. carry a meter with him. We believe that in this case and similar cases, our practice is appropriate and that it is in keeping with the exposure control intent of the present Specification. |
| | III. Conclusion Based on the considerations described above, (l) the proposed, change does not increase the probability or consequences o' accidents or malfunctions of equipment important to safety and does not reduce the margin of safety as defined in the basis for'ny technical specification, therefore, the change does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety o the public. |
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| | |
| | n STATE OF FLORIDA ) |
| | ) ss ~ |
| | COUNTY OF DADE ) |
| | Robert E. Uhrig, being first duly sworn, deposes and says: |
| | That he is a Uice President of Florida Power 6 Light, Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee. |
| | Robert E. Uhrig Subscribed and sworn to before me this Q J~~day of 19~7 NOTARY PUBLIC, in and for the County of Dade, State of Florida NOTARY PUBLIC STATE OF FLORIDA eL LARGE EXPIRES AUGUST 24, LSSI MY COMMISSION L4'ommission expires: BGNDED 'THRU LIAYNARD BGNDIMG AGENGY |
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Category:Letter type:L
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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-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, 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-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - 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Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 L-2023-028, 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 Applications2023-03-27027 March 2023 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-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-01-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-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 ML23275A1142023-10-0202 October 2023 Improved Technical Specifications Conversion, Chapter 2.0, Safety Limits, Revision 1 - Volume 4 L-2023-126, Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal2023-10-0202 October 2023 Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal ML23275A1262023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 5.0, Administrative Controls, Revision 2 - Volume 16 ML23275A1252023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 4.0, Design Features, Revision 2 - Volume 15 ML23275A1242023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.9, Refueling Operations, Revision 2 - Volume 14 ML23275A1232023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.8, Electrical Systems, Revision 2 - Volume 13 ML23275A1222023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.7, Plant Systems, Revision 2 - Volume 12 ML23275A1212023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.6, Containment Systems, Revision 2 - Volume 11 ML23275A1192023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 2 - Volume 9 ML23275A1202023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.5, Emergency Core Cooling Systems, Revision 2 - Volume 10 ML23275A1182023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 2 - Volume 8 ML23275A1162023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 - Volume 6 ML23275A1172023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.2, Power Distribution Limits, Revision 2 - Volume 7 ML23275A1152023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.0, LCO and SR Applicability, Revision 2 - Volume 5 ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 ML23275A1112023-10-0202 October 2023 Improved Technical Specifications (ITS) Revision 2 Submittal Volumes 1 Through 16 ML23275A1122023-10-0202 October 2023 Improved Technical Specifications Conversion License Amendment Request Self-Identified Administrative Changes - Volume 2 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-154, Subsequent License Renewal Application Revision 1, Supplement 42022-09-22022 September 2022 Subsequent License Renewal Application Revision 1, Supplement 4 L-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022 Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal L-2022-043, Subsequent License Renewal Application Revision 1 - Supplement 12022-04-0707 April 2022 Subsequent License Renewal Application Revision 1 - Supplement 1 ML22010A0962022-01-0505 January 2022 Trp 010 St Lucie SLRA - Boricacidcorrbreakoutq - Makar ML21285A1072021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1 ML21285A1082021-10-12012 October 2021 Enclosure 1: St. Lucie Nuclear Plant, Units 1 and 2, Subsequent Licensee Renewal Application, Revision 1 ML21285A1112021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report2021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 ML21215A3152021-08-0303 August 2021 Application for Subsequent Renewed Facility Operating Licenses ML21215A3162021-08-0303 August 2021 Enclosure 1: Subsequent License Renewal Application Enclosures Summary ML21215A3192021-08-0303 August 2021 Appendix E - Applicant'S Environmental Report for St. Lucie L-2021-192, Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-05-26026 May 2021 Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 L-2020-164, License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2020-12-21021 December 2020 License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2020-020, License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years2020-02-18018 February 2020 License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2019-10-0909 October 2019 License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019 Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG L-2018-161, License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2018-12-20020 December 2018 License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2018-182, License Amendment Request Iodine Removal System Elimination2018-11-0909 November 2018 License Amendment Request Iodine Removal System Elimination L-2018-201, Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-0909 November 2018 Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2018-147, Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications2018-08-0202 August 2018 Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications L-2018-121, License Amendment Request to Reduce the Number of Control Element Assemblies2018-06-29029 June 2018 License Amendment Request to Reduce the Number of Control Element Assemblies L-2018-120, License Amendment Request to Remove the Site Area Map from the Technical Specifications2018-06-25025 June 2018 License Amendment Request to Remove the Site Area Map from the Technical Specifications L-2018-111, Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-06-0707 June 2018 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018 Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications L-2018-031, License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme2018-01-31031 January 2018 License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2017-12-19019 December 2017 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors L-2017-139, License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply2017-09-14014 September 2017 License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply 2023-06-14
[Table view] Category:Safety Evaluation
MONTHYEARML23219A0032023-09-0101 September 2023 SLRA SER Rev 1 ML23200A1462023-07-21021 July 2023 Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1 and 2 ML22255A1022022-09-21021 September 2022 Authorization and Safety Evaluation for Alternative Relief Request No. 10 - Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety ML22038A1872022-02-0909 February 2022 Authorization and Safety Evaluation for Relief Request No. 19 (RR19) - the Use of an Alternative to ASME Code Case N-729-6 for Replacement Reactor Vessel Closure Head Penetration Nozzle 85 ML21342A2092022-01-14014 January 2022 Issuance of Amendment Nos. 252 and 207 to Allow Risk-Informed Completion Times (RICT) for the 120-Volt Alternating Current (AC) Instrument Bus Requirements ML21236A1312021-09-30030 September 2021 Authorization of RR 15 Regarding Extension of ASME Requirements Related to Reactor Pressure Vessel Weld Examinations from 10 to 20 Years ML21022A2192021-02-26026 February 2021 Issuance of Amendment No. 206 to Replace the Current Time-Limited Reactor Coolant System Pressure/Temperature Limit Curves and LTOP Setpoints with Curves and Setpoints That Will Remain Effective for 55 Effective Full Power Years ML21027A2262021-02-17017 February 2021 Approval of Alternative to ASME Code, Section XI to Use an Alternative Inservice Inspection Schedule for the Reaction Vessel Closure Head Bolting ML20329A4022021-02-0303 February 2021 Approval of Alternative to Use ASME Code Case N-513-4 for Alternative Repair of Intake Cooling Water System ML20259A2982020-11-18018 November 2020 Issuance of Amendment No. 205 Regarding Modification of the Reactor Coolant Pump Flywheel Inspection Program ML20237F2572020-10-30030 October 2020 Issuance of Amendment Nos. 251 and 204 Regarding Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 Development of Emergency Action Levels for Non-Passive Reactors ML20099A3482020-06-25025 June 2020 Safety Evaluation for Relief Request for Fifth Ten-Year Inservice Inspection (ISI) Interval - Alternative Risk-Informed Inservice Inspection Program for Class 1 and 2 Piping Welds ML20023B3782020-02-19019 February 2020 Safety Evaluation for Relief Request RR-16, Alternate Repair of 2B Boric Acid Makeup Pump Revision for the Fourth 10-Year Inservice Inspection Interval ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19266A0722020-01-27027 January 2020 Issuance of Amendment Nos. 250 and 202 Regarding Technical Specification Changes to Allow the Performance of Selected Emergency Diesel Generator Surveillance Requirements During Power Operation ML19254B5332019-09-30030 September 2019 Safety Evaluation for Relief Request RR#15, Revision 0, Regarding Limited Piping Examinations ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19203A1662019-07-26026 July 2019 Issuance of Exigent Amendment No. 248 Technical Specification 3/4.8.1 Change to Allow for a One-Time Extension of the Allowed Outage Time for One Emergency Diesel Generator ML19115A2812019-05-31031 May 2019 Safety Evaluation for Relief Request No. 6 for the Fifth 10 Year Inservice Inspection Interval ML19058A4922019-04-23023 April 2019 Issuance of Amendment 198 Regarding Technical Specification Changes to Reduce the Number of Control Element Assemblies ML18274A2242018-11-0202 November 2018 Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map ML18256A0982018-10-30030 October 2018 Safety Evaluation for Relief Request No.5 for the Fifth 10-Year Inservice Inspection Interval ML18129A1492018-07-0909 July 2018 Issuance of Amendments Regarding Technical Specification Changes Related to the Auxiliary Feedwater System (CAC Nos. MG0237 and MG0238; EPID L-2017-LLA-0296) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18046A7122018-03-26026 March 2018 Issuance of Amendments Regarding the Unusual Event Fire Related Emergency Action Level Scheme ML18018A0332018-01-26026 January 2018 Safety Evaluation of Relief Requests for the Fifth 10-Year Inservice Testing Program (EPID L-2017-LLR-0113; L-2017-LLR-0017, L-2017-LLR-0018, L-2017-LLR-0119, L-2017-LLR-0120, L-2017-LLR-0121, and L-2017-LLR-0122) ML17334A9362018-01-0404 January 2018 Relief from the Requirements of the ASME Code Regarding Relief Request No. 17, Revision 0, for the Fourth 10-Year Inservice Inspection Interval (CAC No. MF9826; EPID L-2017-LLR-0043) ML17341A4422018-01-0404 January 2018 Relief from the Requirements of the ASME Code Relief Request No. 3 for the Fifth 10-Year Inservice Inspection Interval (CAC No. MF9288; EPID L-2017-LLR-0003) ML17257A0152017-10-31031 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to the Reactor Protection System and Limiting Condition for Operation 3.0.5 ML17263A1202017-10-27027 October 2017 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 16 (CAC No. MF9827; EPID L-2017-LLR-0044) ML17248A3792017-10-23023 October 2017 Issuance of Amendments to Revise the Renewed Facility Operating Licenses Fire Protection License Conditions (CAC Nos. MF9681 and MF9682; EPID L-2017-LLA-0230) ML17235A5652017-10-0505 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to Component Cyclic or Transient Limits ML17219A1742017-08-31031 August 2017 Relief from the Requirements of the ASME Code Regarding Relief Request 12 for the Fourth 10-Year Inservice Inspection Interval ML17195A2912017-08-14014 August 2017 Issuance of Amendments Regarding Relocation of Radiation Monitor Requirements from Technical Specifications to Licensee-Controlled Documents ML17132A1672017-07-10010 July 2017 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 13 ML17110A2702017-05-10010 May 2017 Inservice Inspection Plan Fourth 10-year Interval Relief Request No. 14 Rev 0 - ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17038A2252017-03-29029 March 2017 Issuance of Amendment No. 188 Regarding Emergency Diesel Generator Day Tank Volume ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16251A1282016-12-0505 December 2016 Issuance of Amendments to Update Appendix B to the Renewed Facility Operating License to Incorporate the 2016 Biological Opinion ML16292A7612016-11-0202 November 2016 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 11 ML16166A4242016-10-0505 October 2016 St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendments Regarding the Use of a New Computer Code to Model the Containment Vacuum Analyses ML16183A1382016-09-19019 September 2016 Issuance of Amendments Regarding Technical Specification Change to Eliminate the Moderator Temperature Coefficient Surveillance Test at the End of Cycle ML16210A3742016-08-30030 August 2016 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2 ML16103A3972016-07-28028 July 2016 Issuance of Amendments Regarding Removal of Technical Specification for Cleaning Fuel Oil Storage Tank Sediment and Relocating Procedures to Licensee Controlled Documents ML16167A4732016-07-0505 July 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16139A5882016-05-27027 May 2016 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 10, Revision 0 ML16124A3832016-05-25025 May 2016 St. Lucie Plant, Unit No. 1 - Issuance of Amendment Regarding Changes to the Snubber Surveillance Requirements (CAC No. MF6490) ML16063A1212016-04-19019 April 2016 Redacted - Issuance of Amendment Regarding License Amendment Request for the Transitioning to Areva Fuel ML15344A3462016-03-31031 March 2016 Issuance of Amendments Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) (CAC Nos. MF1373 & MF1374) 2023-09-01
[Table view] |
Text
DISTRIBUTION AFT'SSUANCE 0 PERATING LICENSE NRC ARM $195 U.S. NUCL.EAR REGULATORY COMMi~lON DOCKET NUMBER (Z-7B) t5-
'RC DISTRIBUTION FDR PART 50 DOCKET MATERIAL FILE NUMBER TO FROM: DATE OF DOCUMENT Florida Power & Light Company 12/21/77 Mr. Victor Stello Miami, Florida@ OATS RE CEI V E0 Robert ED Uhrig 12/27/77
~LLUTTER CINOTORIZEO PROP INPUT FORM NUMBER OF COPIFS RECEIVED
~ORIGINAL CJCOPY
~ UN C LASS I F I E 0 DESCRIPTION ENCL OSURE License No. DPR-67 Appl for Amend: tech specs proposed change concerning high radiation area monitoring. ~ ~ inotorized 12/21/77 ~ ~ ~ ~ .
(1-P) (1-P)+(3-P)
PLANT NAME: St. Lucie Unit No. 1
'RJL 12/28/77 SAFETY FOR ACTION/INFORMATION BRANCH CHIEF: 7 INTERNAL 0 IST Rl BUTION REG F I3'. MCGOU EXTERNAL OISTRIBUTION CONTROL NUMBER PDR:
flIC SIC PCRS 1 CYS SEiIT CATEGP 7734soo69
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P.O. BOX 013100, MIAMI, FL 33101 yVll/g e=
FLORIDA PGWER & LIGHT COMPANY December 21, 1977 L-77-388 Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director <<$ !+ lpgpgl<<// 'L,+<<
Division of Operating Reactors '//
U. S. Nuclear Regulatory Commission /<<
(, (<< /I Washington, D. C. 20555
Dear Mr. Stello.:
Re: St. Lucie Unit 1 Docket No. 50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 In accordance with 10 CFR 50.30, Florida Power 6 Light Company submits herewith three (3) signed originals and forty (40) copies of a request, to amend Appendix A of Facility Operating License DPR-67.
The proposed amendment is described below and shown on the accompanying Technical Specification pages bearing the date of this letter in the lower'xight hand coxner.
Specification 6.13 (High Radiation Area) is replaced with the corresponding section from the Standard Technical Specifications.
The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power a Light Company Nuclear Review Board. They have concluded that it: does not. involve an unreviewed
'safety question. A written safety evaluation is attached.
Very truly yours, Robert Z. Uhrig Vice President REU/MAS/cpc Attachment
'~g800 cc: Mr. James P. O'Reilly, Region Robert Lowenstein, Esquire Edward Reeves II 06'9 PEOPLE... SERVING PEOPLE
'
ADMINISTRATIVE CONT I
Unless otherwise authorized by the Commission, the licensee shall not assign protection factors in excess of those specified.
in Table 6.12-1 in selecting and using respiratory protective equipment.
REVOCATION 6.'12.3 The specifications of Section'6.12 shall be revoked in their entir ty upon adoption of'.th proposed chanq to 10 CFP. 20 Section 20.103, which would make such provisions un;ecessary
'
6.13 HIGH RADIATION AREA 633.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c) {2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of' Radiation Vork Permit~.
Any individual or group of individuals p rmitted to e.. -.": such areas shall be provided, with or accoiI.panied by one or more o;:i following=
~
- a. A radiation'monitoring device which continuously indicates the radiation dose rate'n-the area.
- b. .A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is'eceived. Entry into such areas with this
~ rronitoring device may be made. after the dose rata level in 'the area has be n es ablished and personnel have been made knowl-edqeable of- them. '
- c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
.This individual shall be responsible for oroviding posiiive control over the activities within the area and shall perfom periodic radiation surveillance a the frequency specified by the facility Health Physicist in the Padiation bfork Permit 6.j-3.2 The reouirements of 6.g3.l, above, shall also aoply to each hign radiation'rea in which the intensity or radiation is greater than 1000 mrem/hr En addition, locked doors shall be provided to prevent unauthorized'ntry into such areas and the keys shall be maintained under the admin~strative contro1 ' of the Shift Supervisor on duty and/or the Plant H alth Physicist.
~li ment I'. p, 'I I 111 -,p f h R'**
during the performance of their assigned radiation protection duties, provided they compIy with approved radiation protection q
procedur s for entry into high radiation areas.
~ 'I ST. LUCIE -'NIT 1 6-19 3.2/23./77
SAFETY EVALUATION Re: St. Lucie Unit 1 Docket No. 50-335 Hi A Radiation Area Mon~itorin Introduction This evaluation supports a proposed change to Technical Specification 6.13 on administrative control of high radiation areas. The existing Specification is replaced by the corresponding section from the Standard Technical Specifications.
Evaluation The current Specification requires that any individual or group of individuals permitted to enter a high radiation area be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.
For the case of containment entry with the reactor at power, such a -requirement represents good .health physics practice.
It does not, however, guarantee'he intended exposure control in all situations.
For example, when an individual or group of individuals enters a high radiation area which has been surveyed and posted in accordance with the stringent requirements of the Radiation Work Permit (RWP) procedure, a continuously indicating dose rate device located in the same area will not necessarily provide additional exposure control. The device must be read frequently to determine changed.
if radiological conditions have The current Specification does not guarantee that an individual intent on doing his job will also remember to read the radiation monitoring device. Thus, such a device may satisfy the legal requirements of the current Specification without satisfying the intent of the Specification.
Exposure control is achieved in part by administrative pro-cedures that require a radiation survey prior to entry into high radiation areas. Once dose rates are known, Health Physics Department personnel set "stay times" for individuals for the purpose of limiting the individual's accumulated dose. By using one of the proposed alternatives to the current Specification, i.e., the dose integrating/alarming device, we believe that better exposure control is possible. Under this alternative, an individual could have an electronic device attached to his protective clothing, or health physics personnel could set 'up a dose integrating device in the area.
Such devices would have an audible alarm that would annunciate when a preset accumulated dose (determined by health physics personnel) was exceeded. All individuals would be instructed
to leave the work area should an alarm occur.
By using a device with an audible alarm setpoint, personnel would be better protected against the effects of changes in the dose rate. With current practice, a worker cannot become aware of a change in dose rate without periodically monitoring a dose rate device. Thus, the proposed specification is con-servative with respect to the current Specification because does not depend on individuals monitoring their pocket dosi-it meters frequently (as they are instructed to do) or monitoring a separate dose rate device.
We are also proposing an additional alternative to the current specification, i.e., the provision for direct health physics coverage of a job by a health physics qualified individual.
For example, consider the case of steam generator water box entries for the purpose of tube inspection or plugging. Health physics personnel determine the dose rates in the water box, set stay times, and determine what protective clothing must be worn during the entry. Because of the high. dose rates, airborne activity, and contamination, stay times of only minutes are allowed, and a double set of coveralls, a plastic suit, and supplied air are required. During the entry, health physics personnel are at the entrance to the water box to ensure tha" the individual is properly dressed. Once the entry is made, the health physics personnel time the individual to ensure that he minimizes his exposure and does not exceed the plant's administrative exposure limits nor those of the Commission.
Because of the air line and other clothing and equipment that, the individual making the entry must carry into the confined space, and the necessity for short stay times, he cannot. carry a meter with him. We believe that in this case and similar cases, our practice is appropriate and that it is in keeping with the exposure control intent of the present Specification.
III. Conclusion Based on the considerations described above, (l) the proposed, change does not increase the probability or consequences o' accidents or malfunctions of equipment important to safety and does not reduce the margin of safety as defined in the basis for'ny technical specification, therefore, the change does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety o the public.
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n STATE OF FLORIDA )
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COUNTY OF DADE )
Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Uice President of Florida Power 6 Light, Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
Robert E. Uhrig Subscribed and sworn to before me this Q J~~day of 19~7 NOTARY PUBLIC, in and for the County of Dade, State of Florida NOTARY PUBLIC STATE OF FLORIDA eL LARGE EXPIRES AUGUST 24, LSSI MY COMMISSION L4'ommission expires: BGNDED 'THRU LIAYNARD BGNDIMG AGENGY
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