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Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements 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) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program 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-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, 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-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System 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 ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 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 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 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) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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 ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring 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 2024-02-05
[Table view] Category:Safety Evaluation
MONTHYEARML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22193A1142022-09-12012 September 2022 Issuance of Amendment Nos. 270 and 272 Elimination of the Requirements to Maintain the Post-Accident Sampling System ML22140A1272022-05-25025 May 2022 Subsequent License Renewal Application Safety Evaluation Revision 1 Public ML22041A3342022-02-23023 February 2022 Transmittal Letter for Point Beach Final SE for SLRA Review to AA La 2-9 (3) ML22054A1082022-02-23023 February 2022 Subsequent License Renewal Application Safety Evaluation Public ML21148A2552021-07-21021 July 2021 Issuance of Amendment Nos. 269 and 271 Technical Specification Changes to Implement New Surveillance Methods for Transient Heat Flux Hot Channel Factor ML20363A1762021-02-23023 February 2021 Issuance of Amendment Nos. 268 and 270 Regarding Tornado Missile Protection Licensing Basis ML20241A0582020-09-25025 September 2020 Issuance of Amendment No. 267 for One-Time Extension of License Condition 4.I, Containment Building Construction Truss (EPID L-2020-LLA-0180 (COVID-19)) ML20036F2612020-03-0404 March 2020 Approval of Relief Request 1-RR-13 and 2-RR-13 Regarding Extension of Inspection Interval for Point Beach Unit 1 and Unit 2 Reactor Pressure Vessel Welds from 10 to 20 Years ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19339H7472019-12-13013 December 2019 Approval of Relief Request 2-RR-17 Regarding Steam Generator Primary Nozzle Dissimilar Metal Welds Inspection Interval ML19064A9042019-04-25025 April 2019 Issuance of Amendments to Extend Containment Leakage Rate Test Frequency ML19052A5442019-03-27027 March 2019 Issuance of Amendments 264 and 267 to Adopt TSTF-547, Clarification of Rod Position Requirements ML18289A3782018-11-26026 November 2018 Issuance of Amendments to Adopt Title 10 of Code of Federal Regulations 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18079A0452018-06-13013 June 2018 Issuance of Amendments Revision to the Point Beach Nuclear Plant Emergency Action Level Scheme (CAC Nos. MF9859 and MF9860 EPID L-2017-LLS-0278) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML17159A7782017-07-27027 July 2017 Issuance of Amendment to Approve H*: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17039A3002017-02-22022 February 2017 Issuance of Amendments -Removal of Completed License Conditions and Changes to the Ventilation Filter Testing Program 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) ML16241A0002016-09-23023 September 2016 Mitigating Strategies and Spent Fuel Pool Instrumentation Safety Evaluation ML16196A0932016-09-0808 September 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48 (C) ML16118A1542016-06-17017 June 2016 Issuance of Amendments ML16063A0582016-03-22022 March 2016 Approval of Relief Request 2-RR-11; Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection ML16035A5092016-03-0909 March 2016 Correction of Typographical Error in Safety Evaluation Associated with License Amendment Nos. 238 and 242 ML15293A4572015-11-25025 November 2015 Issuance of Amendments for the Steam Generator Technical Specifications, to Reflect Adoption of TSTF-510 ML15246A3052015-09-16016 September 2015 Evaluation of Relief Request RR-10 - Examination of Feedwater Nozzle Extension to Nozzle Weld Fifth 10-Year Inservice Program Interval ML15195A2012015-07-28028 July 2015 Issuance of Amendments Regarding Relocation of Surveillance Frequencies to Licensee Control ML15155A5392015-07-14014 July 2015 Issuance of Amendments Concerning Extension of Cyber Security Plan Milestone 8 ML15161A5352015-06-24024 June 2015 Relief Request VR-01; Alternatives to Certain Inservice Testing Requirements of the American Society of Mechanical Engineers (ASME) Code of Operation and Maintenance of Nuclear Power Plants ML15127A2912015-05-20020 May 2015 Relief Request RR-8, Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Examination of Buried Components ML15099A0182015-05-0707 May 2015 Relief Request RR-9, Proposed Alternative from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for System Leakage Test ML15014A2492015-01-27027 January 2015 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008-01, Managing Gas Accumulation (Tac Nos. MF4353 and MF4354) ML14343A0512014-12-10010 December 2014 Relief from the Requirements of the ASME Code for Re-Examination of the Reactor Pressure Vessel a Inlet Nozzle Weld for the Fifth Ten-Year Inservice Inspection Program Interval ML14293A0022014-10-21021 October 2014 Issuance of Safety Evaluation Regarding Relief Request RR-5 ML14126A3782014-06-30030 June 2014 Issuance of License Amendment Nos. 250 and 254 Regarding Change to Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report ML14058B0292014-05-0909 May 2014 Issuance of Amendment Nos. 249 and 253 Regarding Use of Optimized Zirlo Fuel Cladding Material ML14014A2052014-01-30030 January 2014 Issuance of Relief Request Regarding Risk-Informed Inservice Inspection Program for the Fifth 10-Year Inservice Inspection Interval ML13329A0422013-12-20020 December 2013 Relief from the Requirements of ASME Code, Section XI, for the Fourth 10-Year Inservice Inspection Interval (RR-4L3) ML13329A0312013-12-20020 December 2013 Relief from the Requirements of ASME B&PV Code, Section XI, for the Fourth 10-Year ISI Interval (RR-4L1) ML13346A0402013-12-18018 December 2013 Relief from the Requirements of ASME Code, Section XI, for the Fourth 10-Year Inservice Inspection Interval (RR-4L2) ML13135A2712013-05-29029 May 2013 Safety Assessment in Response to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML13064A4252013-03-18018 March 2013 Relief Request 1-RR-4 Re-Examination of the Unit 1 RPV Indication on the a Inlet Nozzle Weld ML12362A0092013-01-29029 January 2013 Issuance of License Amendment Nos. 248 and 252 Operations Manager Qualification Requirements ML12251A1552012-11-23023 November 2012 Issuance of Amendment to Renewed Facility Operating License Revised Cyber Security Plan Implementation Schedule Milestone 6 2024-01-23
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mm:h 9, 2016 Mr. Eric McCartney Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1AND2- CORRECTION OF TYPOGRAPHICAL ERROR IN SAFETY EVALUATION ASSOCIATED WITH LICENSE AMENDMENT NOS. 238 AND 242
Dear Mr. McCartney:
By letter dated March 25, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110230016), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 238 and 242 to Renewed Facility Operating License Nos. DPR-24 and DPR-27 for Point Beach Nuclear Plant (PBNP), Units 1 and 2, respectively. The amendments modified the licenses and technical specifications (TSs) to support a modification of the motor driven auxiliary feedwater (MDAFW) pumps in the auxiliary feedwater (AFW) system.
On October 15, 2015, the NRC was notified by NextEra Energy Point Beach, LLC (the licensee), that an error had been identified in the safety evaluation (SE) enclosed in the March 25, 2011 letter. Specifically, an error was noted in the discussion of the Completion Time for TS limiting condition for operation (LCO) 3.7.5, Condition C, on page 44 of the SE.
LCO 3.7.5, Condition C, is a condition with the turbine driven auxiliary feedwater (TDAFW) pump system inoperable due to one inoperable steam supply, and the MDAFW pump system inoperable. The Required Action for Condition C is to restore either the steam supply to the TDAFW pump system, or the MDAFW pump system, to operable status. The Completion Time is either 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, depending on the availability of the opposite unit's MDAFW pump system. The existing paragraph in the SE regarding the Completion Time for Condition C reads as follows (emphasis added):
The 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Completion Time is reasonable based a MDAFW pump system being available from the other unit, the capability of this system to provide 100 percent of the AFW flow requirements, and the low probability of an event occurring that would challenge the AFW system. Alternatively, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time applies and is reasonable when a donated MDAFW system is not available from the other unit based on the remaining operable steam supply to the TDAFW pump, the availability of the remaining operable MDAFW pump system, and the low probability of an event occurring that would require the inoperable steam supply to be available for the TDAFW pump.
The emphasized phrase is incorrect because it refers to a "remaining operable MDAFW pump system" that would not be available. The PBNP Final Safety Analysis Report (FSAR), Section
E. McCartney 10.2, "Auxiliary Feedwater," states that the PBNP AFW System consists of one full-capacity MDAFW pump system and one full-capacity TDAFW pump system for each unit, to ensure that adequate feedwater is supplied to the steam generators for heat removal under all circumstances, including loss of offsite power and normal heat sink. Therefore, the above paragraph was in error since it references the remaining operable MDAFW pump. If in LCO 3.7.5, Condition C, the Point Beach Nuclear Plant would not have a remaining operable MDAFW pump system.
The paragraph on page 44 of the SE regarding Completion Time is corrected to read:
The 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Completion Time is reasonable based on a MDAFW pump system being available from the other unit, the capability of this system to provide 100 percent of the AFW flow requirements, and the low probability of an event occurring that would challenge the AFW system. Alternatively, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time applies and is reasonable when a donated MDAFW system is not available from the other unit based on the remaining operable steam supply to the TDAFW pump, and the low probability of an event occurring that would require the inoperable steam supply to be available for the TDAFW pump.
The NRC staff has determined that this was an inadvertent typographical error and is entirely editorial in nature. The proposed correction does not change any of the conclusions in the SE associated with the issuance of Amendment Nos. 238 and 242 for PBNP Units 1 and 2, and does not affect the associated notice to the public. Please find enclosed the replacement page 44 for the SE associated with these amendments. If you have any questions regarding this matter, please contact me at (301) 415-8371.
Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
Corrected Page to Safety Evaluation Associated with License Amendment Nos. 238 and 242 cc w/encl: Distribution via ListServ
ENCLOSURE POINT BEACH NUCLEAR PLANT, UNITS 1AND2 DOCKET NOS. 50-266 AND 50-301 CORRECTED PAGE TO SAFETY EVALUATION ASSOCIATED WITH LICENSE AMENDMENT NOS. 238 AND 242 Page 44
pump due to the faulted SG. In this condition, the AFW system may no longer be able to meet the required flow to the SGs assumed in the safety analysis.
The 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Completion Time is reasonable based on a MDAFW pump system being available from the other unit, the capability of this system to provide 100 percent of the AFW flow requirements, and the low probability of an event occurring that would challenge the AFW system. Alternatively, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time applies and is reasonable when a donated MDAFW system is not available from the other unit based on the remaining operable steam supply to the TDAFW pump, and the low probability of an event occurring that would require the inoperable steam supply to be available for the TDAFW pump.
These changes take advantage of the evolution in policy and guidance as to the required content and preferred format of TS. Therefore, the NRC staff concludes that the proposed changes comply with 10 CFR 50.36 and are acceptable.
CONDITION D
- Replace Condition D, "Required Action and associated Completion Time of Condition A, B, or C not met Two AFW pump systems inoperable in MODE 1, 2, or 3" with:
"Required Action and associated Completion Time of Condition A, B, or C not met."
- Replace Required Action 0.1 Note, "Each unit may be sequentially placed in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when both units are in Condition C concurrently" with:
"Be in MODE 3."
- Replace Required Action D.2 Note, "Entry into MODE 4 is not required unless one motor driven AFW pump system is OPERABLE" with:
"Be in MODE 4."
Condition D is revised to delete the Condition of two AFW pump systems, since the modified AFW system consists of only two pump systems (MDAFW and TDAFW pump systems) per unit.
Loss of both AFW pump systems is covered by Condition E. The Conditions and associated Required Actions are no longer applicable to the unitized AFW system. These changes are administrative technical changes intended to incorporate the use and application principles into the form and structure of TS so that plant operations personnel can use them more easily.
Therefore, the NRC staff concludes that the proposed changes comply with 10 CFR 50.36 and are acceptable.
ML16035A509 p ac k age: ML16067A352 OFFICE DORL/LPLI 11-1 /PM DORL/LPLlll-1/PM DORL/LPLI 11-1 /LA DSS/SBPB/BC NAME ADietrich MChawla MHenderson GCasto DATE 2/03/2016 2/12/2016 2/08/2016 2/23/2016 OFFICE OGC- NLO DORL/LPLlll-1/BC DORL/LPLlll-1/PM NAME BMizuno DWrona MChawla DATE 2/19/2016 3/09/2016 3/09/2016 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mm:h 9, 2016 Mr. Eric McCartney Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1AND2- CORRECTION OF TYPOGRAPHICAL ERROR IN SAFETY EVALUATION ASSOCIATED WITH LICENSE AMENDMENT NOS. 238 AND 242
Dear Mr. McCartney:
By letter dated March 25, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110230016), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 238 and 242 to Renewed Facility Operating License Nos. DPR-24 and DPR-27 for Point Beach Nuclear Plant (PBNP), Units 1 and 2, respectively. The amendments modified the licenses and technical specifications (TSs) to support a modification of the motor driven auxiliary feedwater (MDAFW) pumps in the auxiliary feedwater (AFW) system.
On October 15, 2015, the NRC was notified by NextEra Energy Point Beach, LLC (the licensee), that an error had been identified in the safety evaluation (SE) enclosed in the March 25, 2011 letter. Specifically, an error was noted in the discussion of the Completion Time for TS limiting condition for operation (LCO) 3.7.5, Condition C, on page 44 of the SE.
LCO 3.7.5, Condition C, is a condition with the turbine driven auxiliary feedwater (TDAFW) pump system inoperable due to one inoperable steam supply, and the MDAFW pump system inoperable. The Required Action for Condition C is to restore either the steam supply to the TDAFW pump system, or the MDAFW pump system, to operable status. The Completion Time is either 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, depending on the availability of the opposite unit's MDAFW pump system. The existing paragraph in the SE regarding the Completion Time for Condition C reads as follows (emphasis added):
The 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Completion Time is reasonable based a MDAFW pump system being available from the other unit, the capability of this system to provide 100 percent of the AFW flow requirements, and the low probability of an event occurring that would challenge the AFW system. Alternatively, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time applies and is reasonable when a donated MDAFW system is not available from the other unit based on the remaining operable steam supply to the TDAFW pump, the availability of the remaining operable MDAFW pump system, and the low probability of an event occurring that would require the inoperable steam supply to be available for the TDAFW pump.
The emphasized phrase is incorrect because it refers to a "remaining operable MDAFW pump system" that would not be available. The PBNP Final Safety Analysis Report (FSAR), Section
E. McCartney 10.2, "Auxiliary Feedwater," states that the PBNP AFW System consists of one full-capacity MDAFW pump system and one full-capacity TDAFW pump system for each unit, to ensure that adequate feedwater is supplied to the steam generators for heat removal under all circumstances, including loss of offsite power and normal heat sink. Therefore, the above paragraph was in error since it references the remaining operable MDAFW pump. If in LCO 3.7.5, Condition C, the Point Beach Nuclear Plant would not have a remaining operable MDAFW pump system.
The paragraph on page 44 of the SE regarding Completion Time is corrected to read:
The 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Completion Time is reasonable based on a MDAFW pump system being available from the other unit, the capability of this system to provide 100 percent of the AFW flow requirements, and the low probability of an event occurring that would challenge the AFW system. Alternatively, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time applies and is reasonable when a donated MDAFW system is not available from the other unit based on the remaining operable steam supply to the TDAFW pump, and the low probability of an event occurring that would require the inoperable steam supply to be available for the TDAFW pump.
The NRC staff has determined that this was an inadvertent typographical error and is entirely editorial in nature. The proposed correction does not change any of the conclusions in the SE associated with the issuance of Amendment Nos. 238 and 242 for PBNP Units 1 and 2, and does not affect the associated notice to the public. Please find enclosed the replacement page 44 for the SE associated with these amendments. If you have any questions regarding this matter, please contact me at (301) 415-8371.
Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
Corrected Page to Safety Evaluation Associated with License Amendment Nos. 238 and 242 cc w/encl: Distribution via ListServ
ENCLOSURE POINT BEACH NUCLEAR PLANT, UNITS 1AND2 DOCKET NOS. 50-266 AND 50-301 CORRECTED PAGE TO SAFETY EVALUATION ASSOCIATED WITH LICENSE AMENDMENT NOS. 238 AND 242 Page 44
pump due to the faulted SG. In this condition, the AFW system may no longer be able to meet the required flow to the SGs assumed in the safety analysis.
The 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Completion Time is reasonable based on a MDAFW pump system being available from the other unit, the capability of this system to provide 100 percent of the AFW flow requirements, and the low probability of an event occurring that would challenge the AFW system. Alternatively, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time applies and is reasonable when a donated MDAFW system is not available from the other unit based on the remaining operable steam supply to the TDAFW pump, and the low probability of an event occurring that would require the inoperable steam supply to be available for the TDAFW pump.
These changes take advantage of the evolution in policy and guidance as to the required content and preferred format of TS. Therefore, the NRC staff concludes that the proposed changes comply with 10 CFR 50.36 and are acceptable.
CONDITION D
- Replace Condition D, "Required Action and associated Completion Time of Condition A, B, or C not met Two AFW pump systems inoperable in MODE 1, 2, or 3" with:
"Required Action and associated Completion Time of Condition A, B, or C not met."
- Replace Required Action 0.1 Note, "Each unit may be sequentially placed in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when both units are in Condition C concurrently" with:
"Be in MODE 3."
- Replace Required Action D.2 Note, "Entry into MODE 4 is not required unless one motor driven AFW pump system is OPERABLE" with:
"Be in MODE 4."
Condition D is revised to delete the Condition of two AFW pump systems, since the modified AFW system consists of only two pump systems (MDAFW and TDAFW pump systems) per unit.
Loss of both AFW pump systems is covered by Condition E. The Conditions and associated Required Actions are no longer applicable to the unitized AFW system. These changes are administrative technical changes intended to incorporate the use and application principles into the form and structure of TS so that plant operations personnel can use them more easily.
Therefore, the NRC staff concludes that the proposed changes comply with 10 CFR 50.36 and are acceptable.
ML16035A509 p ac k age: ML16067A352 OFFICE DORL/LPLI 11-1 /PM DORL/LPLlll-1/PM DORL/LPLI 11-1 /LA DSS/SBPB/BC NAME ADietrich MChawla MHenderson GCasto DATE 2/03/2016 2/12/2016 2/08/2016 2/23/2016 OFFICE OGC- NLO DORL/LPLlll-1/BC DORL/LPLlll-1/PM NAME BMizuno DWrona MChawla DATE 2/19/2016 3/09/2016 3/09/2016