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| | number = ML14213A003 | | | number = ML14213A003 |
| | issue date = 08/14/2014 | | | issue date = 08/14/2014 |
| | title = Point Beach Nuclear Plant, Units 1 and 2, Correction to Technical Specification Page 5.6-5 Associated with Amendment Nos. 250 and 254 | | | title = Correction to Technical Specification Page 5.6-5 Associated with Amendment Nos. 250 and 254 |
| | author name = Beltz T A | | | author name = Beltz T |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = McCartney E | | | addressee name = Mccartney E |
| | addressee affiliation = NextEra Energy Point Beach, LLC | | | addressee affiliation = NextEra Energy Point Beach, LLC |
| | docket = 05000266, 05000301 | | | docket = 05000266, 05000301 |
| | license number = DPR-024, DPR-027 | | | license number = DPR-024, DPR-027 |
| | contact person = Beltz T A | | | contact person = Beltz T |
| | case reference number = TAC MF0532, TAC MF0533 | | | case reference number = TAC MF0532, TAC MF0533 |
| | document type = Letter, Technical Specifications | | | document type = Letter, Technical Specifications |
| | page count = 5 | | | page count = 5 |
| | project = TAC:MF0532, TAC:MF0533 | | | project = TAC:MF0532, TAC:MF0533 |
| | stage = | | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Eric McCartney Site Vice President NextEra Energy Point Beach, LLC Point Beach Nuclear Plant, Units 1 and 2 6610 Nuclear Road Two Rivers, WI 54241-9516 August 14, 2014 SUBJECT: POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 -CORRECTION TO TECHNICAL SPECIFICATION PAGE 5.6-5 ASSOCIATED WITH AMENDMENT NOS. 250 (UNIT 1) AND 254 (UNIT 2) Dear Mr. McCartney: On May 9, 2014, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 249 and 253 to Renewed Facility Operating License Nos. DPR-24 and DPR-27 for the Point Beach Nuclear Plant (Point Beach), Units 1 and 2, respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14058B029). The amendments modified the Point Beach technical specifications (TSs) to allow the use of Optimized ZIRLO TM as an approved fuel rod cladding material. The amendments added two additional topical reports to TS Section 5.6.4, "CORE OPERATING LIMITS REPORT (COLR)," and these documents were added to the top of TS page 5.6-5. The addition of these two documents also moved the paragraph forTS Section 5.6.6, "PAM Report," from the bottom of page 5.6-5 to page 5.6-6. On June 30, 2014, the NRC issued Amendment Nos. 250 and 254 (ADAMS Accession No. ML 14126A378) for Point Beach, Units 1 and 2, respectively. The amendments modified the Point Beach TSs to revise TS 5.6.5, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)," to allow the use of two new methodologies for determining RCS pressure and temperature limits. The entirety of TS 5.6.5 is located on TS page 5.6-5. The NRC staff subsequently identified that the TS page 5.6-5, issued with Amendment Nos. 250 and 254, did not include the two topical reports added during issuance of Amendment Nos. 249 and 253, and also continued to include TS Section 5.6.6 at the bottom of the page. Therefore, the purpose of this letter is to correct the two errors on TS page 5.6-5 issued with Amendment Nos. 250 and 254. This letter also will add the appropriate continuation heading forTS Section 5.6.4 to the top of TS page 5.6-5, which was inadvertently omitted during issuance of Amendment Nos. 249 and 253. The NRC staff concludes that the errors were introduced during final preparation and issuance of Amendment Nos. 250 and 254, and are entirely editorial in nature. The proposed corrections do not change any of the conclusions in the safety evaluation associated with the amendments and do not affect the associated notice to the public. Please find enclosed the replacement TS page 5.6-5 to be incorporated during implementation of Amendment Nos. 250 and 254, for Point Beach Units 1 and 2, respectively. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 14, 2014 Mr. Eric McCartney Site Vice President NextEra Energy Point Beach, LLC Point Beach Nuclear Plant, Units 1 and 2 6610 Nuclear Road Two Rivers, WI 54241-9516 |
| E. McCartney -2 -We regret any inconvenience this error may have caused. Docket Nos.: 50-266 and 50-301 Enclosure: Corrected Technical Specification Page 5.6-5 Related to Amendment Nos. 250 and 254 cc w/encl: Distribution via Listserv Sincerely, Terry . Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ENCLOSURE CORRECTED TECHNICAL SPECIFICATION PAGE 5.6-5 RELATED TO AMENDMENT NOS. 250 AND 254 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-266 AND 50-301 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 CORE OPERATING LIMITS REPORT (COLR) (continued) (18) (19) WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995. WCAP-1261 0-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLOŽ," July 2006. c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met. d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC. 5.6.5 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) Point Beach a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, hydrostatic testing, L TOP enabling, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following: b. c. (1) LCO 3.4.3, "RCS Pressure and Temperature (PIT) Limits" (2) LCO 3.4.6, "RCS Loops-MODE 4" (3) LCO 3.4.7, "RCS Loops-MODE 5, Loops Filled" (4) LCO 3.4.1 0, "Pressurizer Safety Valves" (5) LCO 3.4.12, "Low Temperature Overpressure Protection (L TOP)" The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC Letters dated October 6, 2000, July 23, 2001, and October 18, 2007, and June 30, 2014. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto. 5.6-5 Unit 1 -Amendment No. 250 Unit 2 -Amendment No. 254 Revised by correction letter dated August 14, 2014 E. McCartney -2 -We regret any inconvenience this error may have caused. Docket Nos.: 50-266 and 50-301 Enclosure: Corrected Technical Specification Page 5.6-5 Related to Amendment Nos. 250 and 254 cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL3-1 R/F RidsAcrsAcnw_MaiiCTR Resource RidsNrrDorllpl3-1 Resource RidsOgcMaiiCenter Resource ADAMS Accession No* ML 14213A003 .. Sincerely, IRA/ Terry A. Beltz, Senior Project Manager Plant Licensing Branch II 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrLAMHenderson Resource RidsNrrPMPointBeach Resource RidsRgn3MaiiCenter Resource RidsNrrMaiiCenter Resource OFFICE DORLILPL3-1 /PM DORL/LPL3-1 /LA DORLILPL3-1/BC DORL/LPL3-1 /PM NAME TBeltz MHenderson DPelton TBeltz DATE 08/01/2014 08/04/2014 08/14/2014 08/14/2014 OFFICIAL RECORD COPY | | |
| }} | | ==SUBJECT:== |
| | POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION TO TECHNICAL SPECIFICATION PAGE 5.6-5 ASSOCIATED WITH AMENDMENT NOS. 250 (UNIT 1) AND 254 (UNIT 2) |
| | |
| | ==Dear Mr. McCartney:== |
| | |
| | On May 9, 2014, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 249 and 253 to Renewed Facility Operating License Nos. DPR-24 and DPR-27 for the Point Beach Nuclear Plant (Point Beach), Units 1 and 2, respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14058B029). The amendments modified the Point Beach technical specifications (TSs) to allow the use of Optimized ZIRLO TM as an approved fuel rod cladding material. The amendments added two additional topical reports to TS Section 5.6.4, "CORE OPERATING LIMITS REPORT (COLR)," and these documents were added to the top of TS page 5.6-5. The addition of these two documents also moved the paragraph forTS Section 5.6.6, "PAM Report," from the bottom of page 5.6-5 to page 5.6-6. |
| | On June 30, 2014, the NRC issued Amendment Nos. 250 and 254 (ADAMS Accession No. ML14126A378) for Point Beach, Units 1 and 2, respectively. The amendments modified the Point Beach TSs to revise TS 5.6.5, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)," to allow the use of two new methodologies for determining RCS pressure and temperature limits. The entirety of TS 5.6.5 is located on TS page 5.6-5. |
| | The NRC staff subsequently identified that the TS page 5.6-5, issued with Amendment Nos. 250 and 254, did not include the two topical reports added during issuance of Amendment Nos. 249 and 253, and also continued to include TS Section 5.6.6 at the bottom of the page. Therefore, the purpose of this letter is to correct the two errors on TS page 5.6-5 issued with Amendment Nos. 250 and 254. This letter also will add the appropriate continuation heading forTS Section 5.6.4 to the top of TS page 5.6-5, which was inadvertently omitted during issuance of Amendment Nos. 249 and 253. |
| | The NRC staff concludes that the errors were introduced during final preparation and issuance of Amendment Nos. 250 and 254, and are entirely editorial in nature. The proposed corrections do not change any of the conclusions in the safety evaluation associated with the amendments and do not affect the associated notice to the public. Please find enclosed the replacement TS page 5.6-5 to be incorporated during implementation of Amendment Nos. 250 and 254, for Point Beach Units 1 and 2, respectively. |
| | |
| | E. McCartney We regret any inconvenience this error may have caused. |
| | Sincerely, Terry . Beltz, Senior 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 Technical Specification Page 5.6-5 Related to Amendment Nos. 250 and 254 cc w/encl: Distribution via Listserv |
| | |
| | ENCLOSURE CORRECTED TECHNICAL SPECIFICATION PAGE 5.6-5 RELATED TO AMENDMENT NOS. 250 AND 254 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-266 AND 50-301 |
| | |
| | Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 CORE OPERATING LIMITS REPORT (COLR) (continued) |
| | (18) WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995. |
| | (19) WCAP-1261 0-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO'," July 2006. |
| | : c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met. |
| | : d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC. |
| | 5.6.5 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) |
| | : a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, hydrostatic testing, LTOP enabling, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following: |
| | (1) LCO 3.4.3, "RCS Pressure and Temperature (PIT) Limits" (2) LCO 3.4.6, "RCS Loops-MODE 4" (3) LCO 3.4.7, "RCS Loops-MODE 5, Loops Filled" (4) LCO 3.4.1 0, "Pressurizer Safety Valves" (5) LCO 3.4.12, "Low Temperature Overpressure Protection (L TOP)" |
| | : b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC Letters dated October 6, 2000, July 23, 2001, and October 18, 2007, and June 30, 2014. |
| | : c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto. |
| | Point Beach 5.6-5 Unit 1 -Amendment No. 250 Unit 2 -Amendment No. 254 Revised by correction letter dated August 14, 2014 |
| | |
| | * .. ML14213A003 OFFICE DORLILPL3-1 /PM DORL/LPL3-1 /LA DORLILPL3-1/BC DORL/LPL3-1 /PM NAME TBeltz MHenderson DPelton TBeltz DATE 08/01/2014 08/04/2014 08/14/2014 08/14/2014}} |
Letter Sequence Other |
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MONTHYEARNRC 2013-0005, License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-01-15015 January 2013
License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
Project stage: Request
NRC 2013-0022, Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-03-0101 March 2013
Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
Project stage: Supplement
ML13074A0342013-03-12012 March 2013
NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance Review License Amendment Request Associated with TS 5.6.5, RCS PTLR
Project stage: Acceptance Review
ML13098B0702013-03-27027 March 2013
NRR E-mail Capture - Information Needed for Review
Project stage: Other
NRC 2013-0036, Supplement 2 to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2013-04-18018 April 2013
Supplement 2 to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report
Project stage: Supplement
ML13198A1412013-07-11011 July 2013
NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Draft Requests for Additional Information (Evib) Supporting Review of LAR to Implement New PTLR
Project stage: Draft RAI
NRC 2013-0080, License Amendment Request 252 Technical Specification 5.6.5. Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) Response to Request for Additional Information2013-09-12012 September 2013
License Amendment Request 252 Technical Specification 5.6.5. Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) Response to Request for Additional Information
Project stage: Response to RAI
NRC 2014-0016, Submittal of License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)- Response to Request for Additional Information2014-03-11011 March 2014
Submittal of License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)- Response to Request for Additional Information
Project stage: Response to RAI
ML14122A1252014-06-20020 June 2014
Request for Withholding of Proprietary Information from Public Disclosure
Project stage: Withholding Request Acceptance
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
Project stage: Approval
ML14213A0032014-08-14014 August 2014
Correction to Technical Specification Page 5.6-5 Associated with Amendment Nos. 250 and 254
Project stage: Other
2013-07-11
[Table View] |
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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:Technical Specifications
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
ML17159A7782017-07-27027 July 2017
Issuance of Amendment to Approve H*: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region
ML17039A3002017-02-22022 February 2017
Issuance of Amendments -Removal of Completed License Conditions and Changes to the Ventilation Filter Testing Program
NRC 2016-0002, License Amendment Request 280, Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program2016-02-12012 February 2016
License Amendment Request 280, Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program
NRC 2015-0075, License Amendment Request 279, Elimination of Technical Specification 3.7.14, Primary Auxiliary Building Ventilation2016-01-15015 January 2016
License Amendment Request 279, Elimination of Technical Specification 3.7.14, Primary Auxiliary Building Ventilation
ML15232A2082015-08-25025 August 2015
Correction Letter for Amendment Nos. 253 and 257
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
NRC 2015-0027, Response to Request for Additional Information for Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee..2015-05-28028 May 2015
Response to Request for Additional Information for Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee..
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)
ML14213A0032014-08-14014 August 2014
Correction to Technical Specification Page 5.6-5 Associated with Amendment Nos. 250 and 254
NRC 2014-0003, License Amendment Request 273 Re Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program2014-07-0303 July 2014
License Amendment Request 273 Re Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program
NRC-2014-0035, License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2014-07-0202 July 2014
License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
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
NRC 2013-0051, License Amendment Request 272, Exemption Request - Optimized Zirlo Fuel Rod Cladding2013-06-0404 June 2013
License Amendment Request 272, Exemption Request - Optimized Zirlo Fuel Rod Cladding
NRC 2013-0022, Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-03-0101 March 2013
Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
ML12362A0092013-01-29029 January 2013
Issuance of License Amendment Nos. 248 and 252 Operations Manager Qualification Requirements
NRC 2013-0005, License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-01-15015 January 2013
License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
NRC 2012-0065, License Amendment Request 270, Operations Manager Qualification Requirements2012-08-16016 August 2012
License Amendment Request 270, Operations Manager Qualification Requirements
NRC 2012-0033, License Amendment Request 268, Supplement 1, One-Time Only License Amendment to Add Notes for Technical Specifications 3.8.1 and 3.8.2, Actions to Address Nonconformance with Point Beach Nuclear Plant GDC 22012-04-30030 April 2012
License Amendment Request 268, Supplement 1, One-Time Only License Amendment to Add Notes for Technical Specifications 3.8.1 and 3.8.2, Actions to Address Nonconformance with Point Beach Nuclear Plant GDC 2
NRC 2011-0040, License Amendment Request 264, Supplement 1, Diesel Fuel Oil Storage Requirements2011-05-0303 May 2011
License Amendment Request 264, Supplement 1, Diesel Fuel Oil Storage Requirements
NRC 2010-0181, Supplement to License Amendment Request 241 Alternative Source Term Modified License Condition and Technical Specification for Control Room Emergency Filtration System (CREFS)2010-11-16016 November 2010
Supplement to License Amendment Request 241 Alternative Source Term Modified License Condition and Technical Specification for Control Room Emergency Filtration System (CREFS)
NRC 2010-0129, License Amendment Request 261, Supplement 7, Extended Power Uprate2010-08-24024 August 2010
License Amendment Request 261, Supplement 7, Extended Power Uprate
NRC 2010-0112, License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-08-0202 August 2010
License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate
NRC 2010-0040, License Amendment Request 261, Supplement 4 Extended Power Uprate2010-04-15015 April 2010
License Amendment Request 261, Supplement 4 Extended Power Uprate
NRC 2009-0080, License Amendment Request 241, Alternative Source Term, Response to Request for Additional Information2009-08-20020 August 2009
License Amendment Request 241, Alternative Source Term, Response to Request for Additional Information
NRC 2009-0045, Supplement to License Amendment Request 241, Proposed Technical Specifications for Primary Auxiliary Building Ventilation (Vnpab)2009-04-17017 April 2009
Supplement to License Amendment Request 241, Proposed Technical Specifications for Primary Auxiliary Building Ventilation (Vnpab)
NRC 2009-0030, License Amendment Request 261, Extended Power Uprate2009-04-0707 April 2009
License Amendment Request 261, Extended Power Uprate
NRC-2008-0086, License Amendment Request 258 Incorporate Best Estimate Large Break Loss of Coolant Accident (LOCA) Analysis Using Astrum2008-11-25025 November 2008
License Amendment Request 258 Incorporate Best Estimate Large Break Loss of Coolant Accident (LOCA) Analysis Using Astrum
NRC 2008-0034, License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair2008-05-28028 May 2008
License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair
NRC 2008-0018, License Amendment Request 259, Application for Tech Spec Improvement to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to Reactor Coolant System (RCS) Specific Activity Technical Specification2008-03-31031 March 2008
License Amendment Request 259, Application for Tech Spec Improvement to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to Reactor Coolant System (RCS) Specific Activity Technical Specification
NRC 2008-0014, Pressure and Temperature Limits Report2008-02-27027 February 2008
Pressure and Temperature Limits Report
ML0804303372008-02-26026 February 2008
Technical Specification
ML0804303942008-02-19019 February 2008
Tech Spec Page for Amendments 231 and 236 Deletion of Containment Purge Valve Surveillance Requirement
ML0731803152007-11-16016 November 2007
Tech Spec Page for Amendments 230 and 235 TSTF- 491, Revision 2, Removal of Main Steam and Feedwater Valve Isolation Times Technical Specification 3.7.2
ML0721802192007-10-18018 October 2007
Technical Specifications, Revises TS 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) to Add the Ferret Code as an Approved Methodology for Determining RCS Pressure and Temperature Limits
NRC 2007-0051, License Amendment Request 255, Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item..2007-06-29029 June 2007
License Amendment Request 255, Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item..
ML0709502652007-04-0404 April 2007
Technical Specification Pages Steam Generator Tube Repair in the Tubesheet Amendment
ML0705103122007-02-15015 February 2007
Tech Spec Pages for Amendments 224 and 230 Regarding Core Alterations
NRC-2007-0003, Supplement 1 to License Amendment Request 248: Technical Specification 5.5.8, Steam Generator Program2007-01-19019 January 2007
Supplement 1 to License Amendment Request 248: Technical Specification 5.5.8, Steam Generator Program
NRC 2006-0040, License Amendment Request 246 - Deletion of Core Alterations2006-10-23023 October 2006
License Amendment Request 246 - Deletion of Core Alterations
ML0626804152006-09-18018 September 2006
Tech Spec Pages to Correction to Amendment 223 Regarding Steam Generator Tube Integrity
ML0623501982006-08-22022 August 2006
Technical Specifications, Steam Generator Tube Integrity, MD0194 & MD0195
L-HU-06-029, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-07-13013 July 2006
Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
NRC 2006-0061, LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program2006-07-11011 July 2006
LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program
ML0616001172006-06-0808 June 2006
Technical Specifications - Issuance of Amendments Inservice Testing Program
L-HU-06-023, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-05-11011 May 2006
Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
NRC-2006-0032, License Amendment Request 242, Supplement 2 Technical Specification 5.5, Programs and Manuals2006-03-0606 March 2006
License Amendment Request 242, Supplement 2 Technical Specification 5.5, Programs and Manuals
L-HU-06-001, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-02-16016 February 2006
Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
2024-01-23
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 14, 2014 Mr. Eric McCartney Site Vice President NextEra Energy Point Beach, LLC Point Beach Nuclear Plant, Units 1 and 2 6610 Nuclear Road Two Rivers, WI 54241-9516
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION TO TECHNICAL SPECIFICATION PAGE 5.6-5 ASSOCIATED WITH AMENDMENT NOS. 250 (UNIT 1) AND 254 (UNIT 2)
Dear Mr. McCartney:
On May 9, 2014, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 249 and 253 to Renewed Facility Operating License Nos. DPR-24 and DPR-27 for the Point Beach Nuclear Plant (Point Beach), Units 1 and 2, respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14058B029). The amendments modified the Point Beach technical specifications (TSs) to allow the use of Optimized ZIRLO TM as an approved fuel rod cladding material. The amendments added two additional topical reports to TS Section 5.6.4, "CORE OPERATING LIMITS REPORT (COLR)," and these documents were added to the top of TS page 5.6-5. The addition of these two documents also moved the paragraph forTS Section 5.6.6, "PAM Report," from the bottom of page 5.6-5 to page 5.6-6.
On June 30, 2014, the NRC issued Amendment Nos. 250 and 254 (ADAMS Accession No. ML14126A378) for Point Beach, Units 1 and 2, respectively. The amendments modified the Point Beach TSs to revise TS 5.6.5, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)," to allow the use of two new methodologies for determining RCS pressure and temperature limits. The entirety of TS 5.6.5 is located on TS page 5.6-5.
The NRC staff subsequently identified that the TS page 5.6-5, issued with Amendment Nos. 250 and 254, did not include the two topical reports added during issuance of Amendment Nos. 249 and 253, and also continued to include TS Section 5.6.6 at the bottom of the page. Therefore, the purpose of this letter is to correct the two errors on TS page 5.6-5 issued with Amendment Nos. 250 and 254. This letter also will add the appropriate continuation heading forTS Section 5.6.4 to the top of TS page 5.6-5, which was inadvertently omitted during issuance of Amendment Nos. 249 and 253.
The NRC staff concludes that the errors were introduced during final preparation and issuance of Amendment Nos. 250 and 254, and are entirely editorial in nature. The proposed corrections do not change any of the conclusions in the safety evaluation associated with the amendments and do not affect the associated notice to the public. Please find enclosed the replacement TS page 5.6-5 to be incorporated during implementation of Amendment Nos. 250 and 254, for Point Beach Units 1 and 2, respectively.
E. McCartney We regret any inconvenience this error may have caused.
Sincerely, Terry . Beltz, Senior 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 Technical Specification Page 5.6-5 Related to Amendment Nos. 250 and 254 cc w/encl: Distribution via Listserv
ENCLOSURE CORRECTED TECHNICAL SPECIFICATION PAGE 5.6-5 RELATED TO AMENDMENT NOS. 250 AND 254 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-266 AND 50-301
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 CORE OPERATING LIMITS REPORT (COLR) (continued)
(18) WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995.
(19) WCAP-1261 0-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO'," July 2006.
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.6.5 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, hydrostatic testing, LTOP enabling, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
(1) LCO 3.4.3, "RCS Pressure and Temperature (PIT) Limits" (2) LCO 3.4.6, "RCS Loops-MODE 4" (3) LCO 3.4.7, "RCS Loops-MODE 5, Loops Filled" (4) LCO 3.4.1 0, "Pressurizer Safety Valves" (5) LCO 3.4.12, "Low Temperature Overpressure Protection (L TOP)"
- b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC Letters dated October 6, 2000, July 23, 2001, and October 18, 2007, and June 30, 2014.
- c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
Point Beach 5.6-5 Unit 1 -Amendment No. 250 Unit 2 -Amendment No. 254 Revised by correction letter dated August 14, 2014
- .. ML14213A003 OFFICE DORLILPL3-1 /PM DORL/LPL3-1 /LA DORLILPL3-1/BC DORL/LPL3-1 /PM NAME TBeltz MHenderson DPelton TBeltz DATE 08/01/2014 08/04/2014 08/14/2014 08/14/2014
