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Category:Letter type:L
MONTHYEARL-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-014, Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-008, Supplement to 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 Cycles2024-02-0909 February 2024 Supplement to 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-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 2024-08-12
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0 DEC 012011 L-2011-521 FPL.
POWERING TODAY.
EMPOWERING TOMORROW.0 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 Re: Turkey Point Nuclear Generating Station Docket Nos. 50-250 and 50-251 License Amendment Request No. 214 Response to Request for Additional Information Questions
References:
- 1) FPL letter L-2011-046 to the USNRC, dated August 17, 2011, License Amendment Request No. 214, Accident Monitoring Instrumentation Technical Specification Changes Regarding High Range-Noble Gas Effluent Monitors-Main Steam Lines Accident Monitoring Instrumentation
- 2) Email from J. Paige (NRC) to R. J. Tomonto (FPL), "Turkey Point Accident Monitoring Instrumentation TS Changes LAR (ME6891 and ME6892)," dated November 10, 2011 On August 17, 2011, Florida Power and Light Company (FPL) submitted in letter L-2011-046, the License Amendment Request No. 214 (Reference 1) to relocate the Turkey Point Accident Monitoring Technical Specification and Surveillance Requirements for the High Range Noble Gas Effluent Monitor for the Main Steam Lines (RAD-6426) from the Technical Specifications (TS) to the Updated Final Safety Analysis Report (UFSAR) and related procedures.
By electronic mail from the Nuclear Regulatory Commission (NRC) Project Manager (PM) dated November 10, 2011, the NRC requested Florida Power & Light Company (FPL) to respond to request for additional information questions within 30 days (Reference 2).
Attachment 1 contains the NRC RAI questions and the FPL responses. Enclosure 1 provides procedural references to RAD-6426 to facilitate the review of the response to RAI questions.
an FPL Group company
L-2011-521 Page 2 The information provided herein does not change the conclusions stated in Reference 1, and does not create any new commitments.
Should there be any questions, please contact Mr. Robert J. Tomonto, Licensing Manager at 305 246-7327.
Very truly yours, Michael Kiley Vice President Turkey Point Nuclear Plant SM Attachment Enclosure cc: Regional Administrator, USNRC Region II USNRC Senior Resident Inspector - Turkey Point Plant
L-2011-521 Attachment I Page 1 of 2 RAI EICB-1:
Verify that the RAD6426 instrument is not solely credited in any emergency / abnormal operational procedures for an event that involves degradation of the primary coolant boundary (e.g., SG tube rupture). Provide the documentation that demonstrates that RAD6426 has been removed from such procedures.
FPL Response to EICB-1:
The Main Steam Line Monitor, RAD-6426, indication and/or alarms are used in the following off-normal (ONOP) and emergency operating procedures (EOP):
3/4-ONOP-067, "Radioactive Effluent Release" 3/4-ONOP-071.2, "Steam Generator Tube Leakage" 3/4-EOP-FR-H.3, "Response to Steam Generator High Level" 3/4-EOP-E-2, "Faulted Steam Generator Isolation" In each of these procedures, Steam Line Monitor RAD-6426 indication and/or alarms are used as one of several methods available to determine if secondary-side effluent radioactivity has increased, which could be an indication of steam generator tube leakage or tube rupture.
RAD-6426 indications and/or alarms are not used in these procedures as the sole indication of an increase in secondary side radioactivity. For example:
o In 3/4-ONOP-067, an increase in radioactivity (alarm) on either RAD-6426 or RAD-6417 (Condenser Air Ejector radiation monitor) directs the operator to 3/4-ONOP-067 (Steam Generator Tube Leakage).
o In 3/4-EOP-FR-H.3, a check for secondary-side increased radioactivity is made by sampling steam generators, checking RAD-6426 and taking radiation readings on the steam lines.
RAD-6426 indication/alarm is one of several methods available to determine if secondary system activity has increased. It is unlikely that RAD-6426 will detect low levels of radiation increase (due to its higher detection range), before other monitors (such as condenser air ejector and blowdown) detect such increase.
It is concluded that since RAD-6426 is considered as one of several methods available that may be used to determine if secondary activity has increased, it is appropriately included in the station's ONOPs and EOPs.
L-2011-521 Attachment I Page 2 of 2 RAD-6426 monitor is not credited in any of the accident analyses for the prevention or mitigation of any accident. RAD-6426 is not used in any procedure as a sole source of information for operator actions, or in determining if a barrier to fission product release has been breached.
RAD-6426 monitor is credited in the Steam Generator Tube Rupture Radiological Consequences analysis (UFSAR 14.2.4.1) as being available during the event to monitor releases from the Main Steam Safety Valves or Atmospheric Dump Valves.
This use of the monitor is consistent with the definition of a Regulatory Guide 1.97 Type E variable: "those variables to be monitored as required in determining the magnitude of the release of radioactive materials and for continuously assessing such releases".
RAI EICB-2:
RAD6417 was credited as performing the RG 1.97 Type C instrument function that RAD6426 was previously credited regarding detection of a steam generator tube rupture. Are the 19.c entries in Tables 3.3-5 and 4.3-4 of Technical Specification 3.3.3.3 intended to address operability and surveillance of this instrument? Alternately, if this instrument is not addressed in the Technical Specification, explain why.
FPL Response to EICB-2:
Yes, the instrument 19.c entries in Tables 3.3-5 and 4.3-4 of Technical Specification 3.3.3.3 address operability and surveillance requirements specifically for RAD-6417 (Condenser Air Ejector Monitor).
L-2011-521 Enclosure 1 Procedural References Relevant Pages
Procedure No.: Procedure
Title:
Page:
13 Approval Date:
3-ONOP-067 Radioactive Effluent Release 5/27/10 SE I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED r- - - - - - - - - - - - - - - - - - - - - - - -
NOTE I Step 8 is NOT applicable to a channel failure of R-11, R-12, R-15, orR-19. I L. - - - - - - - - - - - - - - -
8 Check For PRMS Channel Failure Perform the following:
" Check Fail indicator - OFF a. IF R-14 fails low AND a gas decay tank release is in progress, THEN stop the
- Display and recorder reading - NOT release.
FAILED LOW
- b. IF R-18 fails low AND a liquid release is in progress, THEN stop the release.
- c. Notify the Shift Manager to refer to Tech Specs AND take all required actions for the failed channel(s).
- d. Notify I&C of the PRMS failure.
9 Check R11/12 RM-80 Green Monitor Light - Identify and correct the cause of failure ON using applicable Steps 18 through 28.
10 Check If Effluent Radiation Monitors ALARMS - OFF
- a. Check the following radiation monitor a. Go to 3-ONOP-071.2, STEAM alarms - OFF GENERATOR TUBE LEAKAGE.
- RAD-3-6426 (DAM-1 Monitor)
- b. Check RAD-6304 (Plant Vent SPING) b. Perform the following as applicable:
alarm - OFF
- 1) 4-ONOP-033.1, SFP COOLING SYSTEM MALFUNCTION
- 2) IF Steps 42 through 45 NOT previously performed, THEN go to Step 42.
- c. Check RAD-6418 (SFP Vent SPING) alarm c. Perform 3-ONOP-033.3, ACCIDENT
- OFF INVOLVING NEW OR SPENT FUEL.
WV97Inw/mr/cla
1.0 PURPOSE 1.1 This procedure provides instructions to be followed in the event of a secondary radiation monitor alarm or malfunction that could result in a radiation hazard or inadvertent release of radioactivity to the environment.
2.0 SYMPTOMS OR ENTRY CONDITIONS 2.1 Alarms on the followina PRMS Channels 2.1.1 Condenser Air Ejector Gas Monitor R-4-15 2.1.2 Steam Generator Liquid Sample Monitor R-4-19 2.2 Hiah Radiation alarms on the following Radiation Monitors 2.2.1 Steam Jet Air Ejector SPING, RAD 6417 2.2.2 DAM-1 Monitor, RAD-6426 2.3 Contr ol Room Annunciators 2.3.1 H 1/4, PRMS HI RADIATION 2.3.2 H 1/6, PRMS CHANNEL FAILURE 2.4 Increasing Count Rate on the following Radiation Monitors 2.4.1 Condenser Air Ejector Gas Monitor R-4-15 2.4.2 Steam Generator Liquid Sample Monitor R-4-19 2.4.3 Steam Jet Air Ejector SPING, RAD 6417 2.4.4 DAM-1 Monitor, RAD-6426 2.5 HP reports high activity on Steam Generator Steam or Blowdown line(s) 2.6 Chemistry reports increasing secondary activity 97*/JEC/ds/ds/cls
STE ACIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check Affected SIG(s) Radiation - NEAR Perform one of the following:
ROUTINE OPERATION VALUE
- IF an E-3 or ECA-3 series procedure is
" Direct Nuclear Chemistry to take activity in effect, THEN return to procedure AND sample of affected S/G step in effect.
" Direct Nuclear Chemistry to check DAM 1 " IF an E-3 or ECA-3 series procedure is monitor reading NOT in effect, THEN go to 4-EOP-E-3, STEAM GENERATOR TUBE
" Direct Radiation Protection to take radiation RUPTURE, Step 1.
readings on main steam line W97:JCIcls