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Category:Letter type:L
MONTHYEARL-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-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule 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-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report 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-2023-028, 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-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results 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-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes 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-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report 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-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
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FPL L-2003-239 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Spent Fuel Pool Cask Area Rack Amendment Clarification on RAI Response to NRC Questions 1Oa and 23 By letter L-2002-214 dated November 26, 2002, Florida Power and Light (FPL) submitted a proposed license amendment to add a spent fuel rack to each unit's spent fuel pool cask area. By letter L-2003-213, dated September 8, 2003 FPL submitted the response to the Request for Additional Information (RAI) for the Addition of Spent Fuel Pool Cask Area Rack Amendment. The responses provided for Questions # 1Oa and # 23 were discussed with the NRC Staff in a telephone conference on September 17, 2003.
The purpose of this letter is to provide a revised response for RAI Question #1 Oa and clarification to the response for RAI Question # 23. Attachment 1 provides the response to RAI Question # 1Oa, which supercedes in its entirety, the response provided in L-2003-213. Attachment 2 clarifies FPL's response to RAI Question # 23 by stating its commitment to Quality Control (QC) hold points in the procedure to verify correct cask area rack orientation. The original No Significant Hazards Determination remains valid with the information provided within.
In accordance with 10 CFR 50.91 (b)(1), a copy of this letter is being forwarded to the State Designee for the State of Florida.
Should there be any questions on this letter, please contact Walter Parker at (305) 246-6632.
Sincerely, i-f;9 T. 0. Jo es Vice President Turkey Point Plant SM Attachments cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point W. A. Passetti, Florida Department of Health C)C an FPL Group company
L-2003-239 Page 2 Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Spent Fuel Pool Cask Area Rack Amendment Clarification on RAI Response to NRC Questions 1Oa and 23 STATE OF FLORIDA )
)ss.
COUNTY OF MIAMI-DADE )
Terry Jones being first duly sworn, deposes and says:
That he is Vice President, Turkey Point Plant, of Florida Power and Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this 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.
- 0. Jones Subscribed and sworn to before me this 30 dayof QLAbe&,2003.
OLGA HANEK cIt
_________________________________________________________________ i MY COMMISSION #CC 926970 Name of Nota/Public (Type or Print) B n. Jne1 TXPIRES wftrs Terry 0. Jones is personally known to me.
Attachment 1 to L-2003-239 Page 1 10 a. The submittal notes that use of divers is not anticipated during the proposed rack installation. However, in the event that divers are needed, what procedural controls will be implemented to ensure that divers maintain a safe distance from any high and very high radiation sources in the pool. Guidance regarding procedural controls is provided in Regulatory Guide 8.38, "Control Of Access To High And Very High Radiation Areas In Nuclear Power Plants", Appendix A, "Procedures For Diving Operations In High and Very High Radiation Areas."
Response
- a. It is FPL policy that the use of divers is a last resort that must be justified from an ALARA perspective. If divers are necessary, the radiological controls will be administered under plant procedure 0-HPS-052.1 0, "Radiological Controls for Diving Operations", which is consistent with the guidance provided in Regulatory Guide 8.38, Appendix A. Under this procedure, appropriate controls will be established, such as a physical barrier (e.g. cage) to prevent the diver from approaching adjacent storage racks. Also, to further reduce the dose rate and risk of high exposure, adjacent racks would be emptied of stored fuel to the extent possible. In addition to a physical barrier that prevents access to adjacent fuel storage areas, the plant will temporarily install warning barricades to alert workers that they have traveled out of the approved dive area. In addition, the rack vendor has a contingency procedure to govern any diver operations, should divers become necessary. The vendor procedure will be reviewed by the Plant Nuclear Safety Committee prior to use.
to L-2003-239 Page 1 Clarification to the Response for RAI Question #23 Introduction The installation procedure for the Turkey Point cask area racks will include Quality Control (QC) hold points. The purpose of the QC hold points will be to verify the racks (one per unit) are correctly oriented by compass direction both before and after their installation in each unit's spent fuel pool. Correct rack orientation is mandatory because one of the four rack sides does not contain Boral neutron-absorbing panels, and the rack criticality analysis requires that the side without Boral panels must face the east pool wall. Because of the rack's rectangular shape and size, it is physically possible to install the rack in either of two rack orientations in the spent fuel pool, 180 degrees apart.
Hereafter, these two orientations are referred to as the 'correct' and the 'backward' orientations. The rack is not allowed to be installed in the backward orientation because the rack side without Boral panels would then face other fuel storage racks instead of the pool wall, invalidating the rack criticality analysis.
Correct Rack Orientation See Figures 1 and 2 on the following page for the correct rack orientation in the Unit 3 and Unit 4 spent fuel pools, respectively.
Note that on both units, the rack face with no Boral panels faces the east pool wall; the notched (excluded) corner cell is adjacent to the east pool wall; and the rack nameplate is on the north rack face.
Description of QC Hold Points The rack installation procedure QC hold points will require an authorized QC inspector to independently verify and sign the procedure at two different times (before and after rack installation) that the rack is correctly oriented. Orientation will be determined by comparing physical rack features with specific compass directions, as described below.
At each hold point, QC signoff will be required before the rack installation will be allowed to continue.
Two QC hold points will be included in each unit's installation procedure. The hold points take the form of a boxed note inserted between procedure steps similar to:
QC HOLD POINT Level I or higher QC Inspector (any discipline) shall:
- Verify the proper completion of Steps xxx and yyY
- Sign Data Sheet X in space provided to L-2003-239 Page 2 UNIT 3 SPENT FUEL POOL (other spent fuel racks not shown)
North -_
Cask Area Rack 1*T1 I rI Notched (excluded) comer cell Nameplate on for storing Fuel Handling Tool north rack face No Boral panels on,,
east rack face Figure 1 Correct Unit 3 Rack Orientation UNIT 4 SPENT FUEL POOL (other spent fuel racks not shown)
North -- +
Cask Area Rack I II" I A1II I I _a I
_I0 Nameplate on I _ north rack face
_r~~~~~~~~~~~
I _2 ZC II I
No Boral panels on. t Notched (excluded) corner cell east rack face for storing Fuel Handling Tool Figure 2 Correct Unit 4 Rack Orientation to L-2003-239 Page 3 Description of QC Hold Points (continued)
The two QC hold points will include instructions similar to the following:
- 1. Prior to rack installation, the rack will be staged out-of-doors east of the appropriate unit's Auxiliary Building L-shaped door under the cask handling crane. A QC hold point will require verification of the following steps:
- With the cask area rack on the leveling pad located under the cask handling crane, verify that the rack nameplate is facing north (the nameplate is located near the top of the north rack face, near the northeast corner).
- Verify that the nameplate reads 'Turkey Point Unit 3". ["Unit 4" in the Unit 4 procedure]
- Verify that the notch (excluded cell) in the rack corner is in the southeast corner of the Unit 3 rack. [northeast corner of the Unit 4 rack]
With these three conditions met, the rack is correctly oriented for installation. The cask crane and rack lifting rig will maintain the correct orientation during rack lifting, transfer through the L-shaped door, and lowering into the spent fuel pool cask area.
- 2. Following rack installation in the spent fuel pool cask area, a QC hold point will require verification of the following step:
- Verify by visual observation that the notch (excluded cell) is adjacent to the east pool wall, in the southeast corner of the Unit 3 rack. [northeast corner of the Unit 4 rack]
Satisfying each QC hold point will be indicated by a QC inspector signature and date on a data sheet in the procedure.
The second QC hold point (confirmation of the notched cell along the east wall) provides positive proof that the rack is installed in the correct orientation. If the rack were backwards, the missing cell would not be visible along the wall, and no storage location would be available for the fuel handling tool.
Identifying the commitment in the procedure In addition to the QC hold points, a precaution statement will be added to the Precautions/
Limitations section of the rack installation procedure identifying the hold points as a plant licensing commitment and referencing the appropriate FPL or NRC letter that includes the commitment.