|
---|
Category:Letter type:L
MONTHYEARL-2024-085, Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results2024-10-15015 October 2024 Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results L-2024-165, Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made2024-10-14014 October 2024 Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-155, Subsequent License Renewal Application, Third Annual Update2024-09-27027 September 2024 Subsequent License Renewal Application, Third Annual Update L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-117, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage 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-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review L-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-027, Safety Injection Tank Vent Through Wall Leakage2024-02-29029 February 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-175, 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-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report 2024-09-09
[Table view] |
Text
0 January 27, 2014 FPL. L-2014-020 10 CFR 50.54(0 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Units I and 2 Docket Nos. 50-335 and 50-389 Renewed Facility Operating License Nos. DPR-67 and NPF-16 Update to Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Flooding - Review of Available Physical Margin (APM) Assessments
References:
(1) NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(0 Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident," dated March 12, 2012, Accession No. ML12073A348.
(2) NRC Letter to Nuclear Energy Institute, "Endorsement of Nuclear Energy Institute (NEI) 12-07,
'Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features,"' dated May 31, 2012, Accession No. MLI 2144A 142.
(3) Florida Power & Light (FPL) Letter L-2012-428, dated November 27, 2012, "Response to NRC 10 CFR 50.54(0 Request for Information Regarding Near-Term Task Force Recommendation 2.3, Flooding, St. Lucie Plant Units 1 and 2, Flooding Walkdown Report FPL060-PR-001, Rev.0" (4) NRC Letter, "Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns," dated December 23, 2013, Accession No. MLI 3325A891 (5) St. Lucie Corrective Action Program (CAP) Action Request (AR) 1748014, Assignment 04, Small APM Justification.
(6) St. Lucie Corrective Action Program (CAP) Action Request (AR) 1931279, Assignment 01, Penetration Seal APM Justification.
On March 12, 2012, the N RC staff issued Reference I requesting information pursuant to Title 10 of the Code of Federal Regulations 50.54(0. Enclosure 4 of that letter contains specific Requested Information associated with Near-Term Task Force Recommendation 2.3 for Flooding. Per Reference 2, the NRC endorsed Nuclear Energy Institute (NEI) 12-07, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features," dated May 31, 2012. By Reference 3, Florida Power & Light (FPL) submitted the final report in response to the request for information.
One of the requirements of NEI 12-07 is to identify the available physical margin (APM) associated with each applicable flood protection feature, determine if the margin provided is small, and evaluate any small margins that have potentially significant consequences through the corrective action process. The results of this effort were to be maintained on site for future NRC audits.
Florida Power &Ught Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
L-2014-020 Page 2 Following the NRC staff's initial review of the walkdown reports, regulatory site audits were conducted at a sampling of plants. Based on the walkdown report reviews and site audits, the staff identified additional information necessary to allow them to complete its assessments. Accordingly, by Reference 4 the NRC staff has issued a request for additional information (RAI). The attachment to this letter provides FPL's responses for the St. Lucie Plant.
This letter contains no new Regulatory Commitments and no revision to existing Regulatory Commitments.
Should you have any questions regarding this submittal, please contact Eric S. Katzman, St. Lucie Licensing Manager, at 772-467-7734.
I declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge.
Executed on January 2 -- ,2014 Very Joseph Jensen Site Vice President St. Lucie Plant Attachment
L-2014-020 Attachment Page I of 2 Per (4) NRC Letter, "Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns," dated December 23, 2013, Accession No. ML13325A891, FPL provides the following responses.
RAI Number 1: Confirmation that the processfor evaluatingAPM was reviewed Response: FPL has completed a review of the process used at the St. Lucie Plant to evaluate APMs.
RAI Number 2: Confirmation that the APM process is now or was always consistent with the guidance in NEI 12-07 and discussed in this RAI.
Response: The APM process used at St. Lucie Plant followed the guidance provided in NEI 12-07, including a definition for a small margin. Additional actions have been taken to make the process consistent with the information provided in this RAI.
RAI Number 3: If changes are necessary, a general descriptionof any process changes to establish this consistency.
Response: As stated above, the APM process used at St. Lucie Plant followed the guidance provided in NEI 12-07, including a definition for a small margin (AR 1748014, Reference 5). However, a specific APM had not been assigned to the seals associated with flood protection features. These items have now been addressed in accordance with the guidance provided in this RAI and entered into the corrective action process (AR 1931279, Reference 6), as appropriate, for further evaluation.
RAI Number 4: As a result of the audits and subsequent interactionswith industry duringpublic meetings, NRC staff recognized that evaluation ofAPMfor seals (e.g., flood doors, penetrations,floodgates, etc.)
was challengingfor some licensees. Generally, licensees were expected to use either Approach A or Approach B (describedbelow) to determine the APMfor seals.-
a) If sealpressure ratings were known, the seal ratings were used to determine APM (similarto example 2 in Section 3.13 ofNEI12-07). A numericalvalue for APM was documented No further action was performed if the APM value was greater than the pre-establishedsmall-margin threshold value. If the APM value was small, an assessment of "significantconsequences" was performed and the guidance in NEI 12-07 Section 5.8 was followed b) If the seal pressure ratingwas not loiown, the APMfor seals in aflood barrieris assumed to be greater than the pre-establishedsmall-marginthreshold value if the following conditions were met:
(1) the APMfor the barrierin which the seal is located is greater than the small-margin threshold value and there is evidence that the seals were designed/procured,installed,and controlled as flooding seals in accordancewith the flooding licensing basis. Note that in order to determine that the seal has been controlledas afloodingseal, it was only necessary to determine that the seal conifigurationhas been governed by the plant's design controlprocess since installation. In this case, the APMfor the seal could have been documented as "not small ".
L-2014-020 Attachment Page 2 of 2 As part of the RAI response, state if either Approach A or Approach B was used as part of the initial walkdowns or as part of actions taken in response to this RAI. No additionalactions are necessary if either Approach A or B was used.
If neitherApproach A or B was used to determnine the APM values for seals (eitheras part of the walkdowns or as part of actions taken in response to this RAI), then perform the following two actions:
- Enter the condition into the CAP (note: it is acceptableto utilize a single CAP entry to capture this issuefor multiple seals). CAP disposition of "undetermined" APM valuesfor seals should consider the guidanceprovided in NEI 12-07, Section 5.8. The CAP disposition should confirm all seals can perform their intended safetyfunction againstfloods up to the currentlicensing basisflood height.
Disposition may occur as part of the IntegratedAssessment. If an IntegratedAssessment is not performed,determine whether there are significant consequences associatedwith exceeding the capacity of the seals and take interim action(s), if necessary, via the CAP processes. These actions do not need to be complete prior to the RAI response.
- Report the APMas "undetermined" andprovide the CAP reference in the RAI response.
Response: Neither Approach A or B, as described above, were used to determine the APM values for seals. As part of the actions taken to address this RAI, the seals have been assigned an APM value of "undetermined" and have been entered into the CAP process (ARs 1748014 and 1931279, References 5 and 6) for further evaluation of their available physical margin. The disposition of the Action Requests will determine the APM and implementation of interim actions will be pursued, if necessary.
In addition, the original walkdown record forms issued as Attachment C to Reference 3 assigned an APM value of"N/A" for features (seals) located below the plant flood level. St. Lucie's intent is to not revise Attachment C to reflect the change in APM value from "N/A" to "undetermined," rather justification for the use of APM valve "N/A" will be included as part of the CAP entry (Reference 6).