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Category:Letter type:NRC
MONTHYEARNRC 2023-0013, Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-07-0707 July 2023 Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations NRC 2023-0006, Post-Exam Submittal Cover Letter2023-03-0101 March 2023 Post-Exam Submittal Cover Letter NRC 2023-0005, Report of Changes to Emergency Plan2023-02-21021 February 2023 Report of Changes to Emergency Plan NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System NRC 2022-0019, Report of Changes to Emergency Plan2022-07-13013 July 2022 Report of Changes to Emergency Plan NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, NRC 2022-0015, Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report2022-04-27027 April 2022 Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report NRC 2022-0014, 2021 Annual Monitoring Report2022-04-14014 April 2022 2021 Annual Monitoring Report NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process2022-03-25025 March 2022 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2022-02-22022 February 2022 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections NRC 2022-0004, Report of Changes to Emergency Plan2022-02-0909 February 2022 Report of Changes to Emergency Plan NRC 2022-0005, Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2022-0001, Report of Changes to Emergency Plan2022-01-11011 January 2022 Report of Changes to Emergency Plan NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2021-0031, Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-0562021-07-15015 July 2021 Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-056 NRC 2021-0027, Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-0532021-06-30030 June 2021 Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-053 NRC 2021-0028, Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism2021-06-23023 June 2021 Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism NRC 2021-0021, 2020 Annual Monitoring Report2021-04-29029 April 2021 2020 Annual Monitoring Report NRC 2021-0019, Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations NRC-2021-0010, CFR 50.59 Evaluation and Commitment Change Summary Report2021-04-0202 April 2021 CFR 50.59 Evaluation and Commitment Change Summary Report NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2021-0006, Report of Changes to Emergency Plan2021-03-18018 March 2021 Report of Changes to Emergency Plan NRC 2021-0005, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-022021-02-11011 February 2021 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-02 NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report NRC 2021-0001, Report of Changes to Emergency Plan2021-01-13013 January 2021 Report of Changes to Emergency Plan NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 NRC 2020-0029, Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-09-15015 September 2020 Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0023, NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-08-12012 August 2020 NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2020-0018, Report of Changes to Emergency Plan2020-07-15015 July 2020 Report of Changes to Emergency Plan NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0008, Report of Changes to Emergency Plan2020-04-0606 April 2020 Report of Changes to Emergency Plan NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0044, Report of Changes to Emergency Plan2019-11-0101 November 2019 Report of Changes to Emergency Plan NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2019-0037, Technical Specification Bases Change Summary2019-10-18018 October 2019 Technical Specification Bases Change Summary NRC 2019-0034, Technical Requirements Manual Change Summary2019-10-18018 October 2019 Technical Requirements Manual Change Summary NRC 2019-0032, CFR 50.59 Evaluation and Commitment Change Summary Report2019-10-18018 October 2019 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information 2023-07-07
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NMC Excellence Committed to Nuclear Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC August 30, 2004 NRC 2004-0089 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 License Nos. DPR-24 and DPR-27 Relief Requests from the Provisions of ASME Section Xl, IWA-5244, "Buried Components," RR-1-26 and RR-2-34 In accordance with 10 CFR 50.55a(g)(5)(iii), Nuclear Management Company, LLC (NMC), licensee for Point Beach Nuclear Plant (PBNP), hereby requests relief from the requirements of 1986 Section Xl, IWA-5244, "Buried Components," for PBNP Units 1 and 2, for the third inservice interval, which ended on June 30, 2002. The basis for the request is that compliance with the specified requirements was impractical. Performing the specified examinations would have required excavation of buried piping, between the circulating water pump house and the turbine building, without a compensating increase in the level of quality and safety.
This issue was identified during an NRC inspection of the PBNP service water (SW) system. A review of previous PBNP pressures tests indicated that prior Inservice Inspection.(lSI) intervals had not met Code requirements for performing pressure testing on buried portions of the main SW headers as required by IWA-5244. NMC recognizes that this request should have been submitted within 12 months of the end of the effective interval and has addressed this issue via the PBNP corrective action process.
This letter contains no new commitments and no revisions to existing commitments.
Dennis L. Koehl Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC Enclosure ,0C `
6590 Nuclear Road
- Two Rivers, Wisconsin 54241 Telephone: 920.755.2321
Document Control Desk Page 2 cc: Administrator, Region III, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Mike Verhagen, Department of Commerce, State of Wisconsin
ENCLOSURE 1 RELIEF REQUESTS RR-1-26 AND RR-2-34 REQUEST FOR RELIEF FROM EXAMINATION OF BURIED SERVICE WATER PIPING Pursuant to 10 CFR 50.55a(g)(5)(iii), Nuclear Management Company, LLC (NMC),
requests relief from the requirements of 1986 Section Xi, IWA-5244, 'Buried Components." The basis for the request is that compliance with the specified requirements is impractical. Performing the specified examinations would require excavation of buried piping, between the circulating water pump house and the turbine building, without a compensating increase in the level of quality and safety.
ASME Code Components Affected PBNP, Units 1 and 2 Class 3 Service Water (SW) piping running from the intake structure to the turbine building. Approximately 90 feet of piping for each unit is buried and not accessible for pressure testing.
Applicable Code Edition and Addenda
ASME Section Xl, 1986 Edition, no Addenda
Applicable Code Requirement
IWA-5211 Test Description - The pressure retaining components within each system boundary shall be subject to system pressure tests under which conditions visual examination VT-2 is performed in accordance with IWA-5240 to detect leakages. The required system pressure tests and examinations, as referenced in Table IWA-5210-1, may be conducted in conjunction with one or more of the following system tests or operations: ...
(c) a system inservice test conducted to perform visual examination VT-2 while the system is in service under operating pressure; IWA-5223 - System Inservice Test Boundary - The boundary subject to test pressurization during a system inservice test [IWA-5211 (c)] shall extend to those pressure-retaining components under operating pressures during normal system service.
Examination Category D-B, Item No. D2.10, Pressure retaining components, extent of examination is the pressure-retaining boundary.
IWA-5244 was determined to not have a method for testing redundant, isolable buried piping segment. The buried piping in the Service Water system is redundant (ring header provides this ability) and is isolable against a header piping break.
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Reason for Request===
The buried piping consists of about 90 feet of 30-inch diameter piping located between the intake structure and the turbine building. There is no access to this buried piping other than excavation. No annulus was provided during original construction as a means for testing this buried section.
One possible alternative is to isolate the buried section of the system and perform a test that determines the rate of pressure loss. This test method is a stated method in ASME Section XI, 1998 Edition, 2000 Addenda, IWA-5244(b)(1). This test would require entry into a dual unit Technical Specification Action Condition. The current isolation valves available to isolate this buried portion of piping are butterfly valves. These valves are designed to isolate a failed ring header such that the remaining portion of the ring header would still provide the required system flow; however, the valves are not expected to provide an adequate pressure test boundary, which is necessary for accurate pressure test results. System modification would be required to perform this type of test, as it would be necessary to replace the valves with those of better leakage characteristics or provide blank flanges that could be installed temporarily to conduct this test.
The 1986 edition also states that as an alternative, a test to determine the change in flow between the ends of the buried piping is allowed. The SW system is not instrumented to make this determination. To use an ultrasonic flow meter would require a length of straight pipe 15 times its diameter. As-built drawings of the system show a 12 foot 3 inch straight length of piping with a 24 inch by 30 inch reducer. The ultrasonic gauge would require a 30 foot length of straight piping without turbulence-inducing components to work correctly. Plant experience has shown that 15 pipe diameters of straight length piping is the minimum length required in order to get an accurate rate of flow.
The SW system for both units is configured with a ring header such that both sides of the system are supplying both units. PBNP Technical Specification (TS) 3.7.8 requires, "Service Water ring header continuous flow path not interrupted." Removing one section of the ring header from service reduces the redundancy of the system. If the SW ring header continuous flowpath is interrupted, the ability of the system to provide required cooling water flow to required equipment must be verified within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per PBNP TS 3.7.8. Isolating a section of the SW ring header also requires entry into a 7-day TS Action Condition to restore the flow path.
The possibility of erosion from Microbiologically Influenced Corrosion (MIC) is low in this section of piping. This is due to the continuous high flow rate of water through the piping, which does not support significant microbiological attack.
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Proposed Alternative and Basis for Use NMC proposes to use Inservice Testing procedures to verify adequate flow through the system. The Inservice Testing procedures are for quarterly testing of the SW pumps.
This proposed alternative will confirm unimpaired flow as stated in ASME Section Xl, 1998 Edition, 2000 Addenda, as currently approved by 10 CFR50.55a(b)(2). Paragraph IWA-5244, "Buried Components," states, "(2) The system pressure test for nonisolable buried components shall consist of a test to confirm that flow during operation is not impaired."
The buried portion of pipe is isolable to protect against a header break but not sufficiently isolable for a pressure test. Application of IWA-5244(2) will provide an adequate level of quality and safety. The use of the inservice pump test provides a means to ensure flow during operation is not impaired. The pump acceptance criteria also ensure the required safety flow is maintained for any buried piping leakage, other than system loss of flow and pump degradation. Significant through-wall leakage of a buried pipe would result in a failed inservice pump test for three of six service water pumps providing flow to this portion of buried pipe. This failure would result in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> technical specification action condition and lead to a plant shutdown to identify and correct the condition.
Duration of Proposed Alternative The duration of the proposed alternative is for the third inservice interval, which ended on June 30, 2002.
References ASME Section Xl, 1986 Edition ASME Section Xi, 1998 Edition with Addenda through 2000 EPRI TM-I1001, Microbiologically Influenced Corrosion PBNP Technical Specification 3.7.8, Service Water (SW) System Page 3 of 3