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Category:Code Relief or Alternative
MONTHYEARML24068A2492024-04-22022 April 2024 – Authorization and Safety Evaluation for Alternative Request No. I6-RR-01 ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval 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 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 ML19339H7472019-12-13013 December 2019 Approval of Relief Request 2-RR-17 Regarding Steam Generator Primary Nozzle Dissimilar Metal Welds Inspection Interval ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques L-2017-121, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-07-24024 July 2017 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography 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) ML16063A0582016-03-22022 March 2016 Approval of Relief Request 2-RR-11; Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection 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 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 NRC 2015-0025, Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B2015-05-14014 May 2015 Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B 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 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 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) ML13079A1412013-03-19019 March 2013 CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval NRC 2013-0020, CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval2013-03-19019 March 2013 CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval ML13064A4252013-03-18018 March 2013 Relief Request 1-RR-4 Re-Examination of the Unit 1 RPV Indication on the a Inlet Nozzle Weld ML12286A1042012-11-15015 November 2012 Evaluation of Relief Requests RR-2 & RR-3 (ME7974 & ME7975) ML0617103642006-07-0303 July 2006 Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 - Use of ASME Code Case N-513-2 ML0527001972006-01-18018 January 2006 Relief Request - Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 2 ML0526503122005-09-27027 September 2005 Relief Requests - the Previsions of ASME Section XI, IWA-5244, Buried Components, RR-1-26 and RR-2-34 NRC 2005-0084, Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 22005-07-0101 July 2005 Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 2 NRC 2005-0016, Relief Request from the Provisions of ASME Section Xl, IWA-4422.2.2, Defect Removal Followed by Welding or Brazing, Relief Request 162005-02-0404 February 2005 Relief Request from the Provisions of ASME Section Xl, IWA-4422.2.2, Defect Removal Followed by Welding or Brazing, Relief Request 16 NRC 2005-0015, Relief Request from the Provisions of ASME Section XI, IWA-5244, Buried Components, Relief Request 152005-01-21021 January 2005 Relief Request from the Provisions of ASME Section XI, IWA-5244, Buried Components, Relief Request 15 ML0408601612004-04-0101 April 2004 Request for Relief VRR 03-01 on a One Time Basis for Performing Inservice Testing of Relief Valve 1RH-861C ML0401607382004-02-26026 February 2004 Prairie, Units 1 and 2, Kewaunee, Point Beach, Units 1 and 2, Palisades, Re Request for Alternatives to ASME Section XI, Appendix Viii, Supplement 10 ML0323104022003-09-10010 September 2003 Relief, MR 02 018-2 Pertaining to Reactor Vessel Closure Head Penetration Repair ML0306203282003-03-21021 March 2003 Relief, Use of Code Case N-600 for the Fourth 10-Year Interval, MB5403 and MB5404 ML0225401092003-03-21021 March 2003 Relief Request No 8 - Requirement for Scheduling of Components for Examination ML0302101262003-02-27027 February 2003 Relief, Alternative to Examine All Three Vessels of the Regenerative Heat Exchanger, MB5401 & MB5402 ML0225300232002-10-0808 October 2002 Relief, Granted for ASME Code Section XI, Relief Request 6 Regarding Evaluation of Leakage with Bolting In-Place ML0225300062002-10-0808 October 2002 Code Relief, ASME Code Section XI, Relief Request 5 Regarding Visual Examination of Insulted Bolting on Borated Systems NRC 2002-0073, Reactor Vessel Closure Head Penetration Repair Relief Requests MR 02-018-1 and MR 02-018-22002-08-28028 August 2002 Reactor Vessel Closure Head Penetration Repair Relief Requests MR 02-018-1 and MR 02-018-2 2024-04-22
[Table view] Category:Letter type:NRC
MONTHYEARNRC 2024-0007, Ile Post-Exam Submittal Letter2024-03-18018 March 2024 Ile Post-Exam Submittal Letter NRC-2024-0026, Ile Proposed Exam Submittal Letter2023-12-20020 December 2023 Ile Proposed Exam Submittal Letter NRC 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 2024-03-18
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NMCh Committed to Nuclear Excellence Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC January 21, 2005 NRC 2005-0015 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 Request from the Provisions of ASME Section Xl, IWA-5244. "Buried Components." Relief Request 15 In accordance with 10 CFR 50.55a(a)(3)(ii), Nuclear Management Company, LLC (NMC), licensee for Point Beach Nuclear Plant (PBNP), hereby requests relief from the requirements of the 1998 Edition with Addenda through 2000 of Section Xl, IWA-5244, "Buried Components," for PBNP Units 1 and 2, for the fourth inservice interval, which began on July 1, 2002 and ends on June 30, 2012. The basis for the request is that compliance with the specified requirements is a hardship without a compensating increase in the level of quality and safety. Performing the specified examinations will require excavation of buried piping between the Circulating Water Pump House and the Turbine Building, reconfiguration of the existing Service Water system, and/or entry into a dual unit seven-day Technical Specification Action Condition.
A review of previous PBNP pressures tests indicated that prior Inservice Inspection (ISI) intervals had not met Code requirements for performing pressure testing on buried portions of the main SW headers as required by IWA-5244 of the 1986 Edition of ASME Section Xl. By letter dated August 30, 2004, NMC submitted a separate relief request regarding that issue.
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 6590 Nuclear Road
- Two Rivers, Wisconsin 54241 dz4 Telephone: 920.755.2321
Document Control Desk Page 2 Enclosure cc: Administrator, Region 111, 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 REQUEST 15 REQUEST FOR RELIEF FROM THE EXAMINATION REQUIREMENTS OF ASME SECTION XI, IWA-5244, "BURIED SERVICE WATER PIPING" Pursuant to 10 CFR 50.55a(a)(3)(ii), Nuclear Management Company, LLC (NMC),
requests relief from the requirements of 1998 Edition with Addenda through 2000 of Section Xl, IWA-5244, "Buried Components." The basis for the request is that compliance with the specified requirements is a hardship without a compensating increase in the level of quality and safety. Performing the specified examinations will require excavation of buried piping between the Circulating Water Pump House and the Turbine Building, reconfiguration of the existing Service Water (SW) system, and/or entry into a dual unit seven-day Technical Specification Action Condition (TSAC).
ASME Code Components Affected Approximately 90 feet of Class 3, 30-inch diameter cast steel SW piping for each unit buried between the Circulating Water Pump House and the Turbine Building.
These sections of piping are not accessible for pressure testing.
Applicable Code Edition and Addenda
ASME Section Xl, 1998 Edition with Addenda through 2000 Applicable Code Requirements IWA-521 1, 'Test Description" Pressure retaining components within each system boundary shall be subject to the following applicable system pressure tests referenced in Table IWA-5210-1 under which conditions a VT-2 visual examination is performed in accordance with IWA-5240 to detect leakage:
(a) a system leakage test conducted while the system is in operation, during a system operability test, or while the system is at rest conditions using an external pressurization source.
IWA-5221, "System Leakage Test Boundary" The boundary subject to test pressurization during a system leakage test
[IWA-5211 (a)] includes the pressure retaining components to be tested in accordance with IWB-5222, IWC-5222, and IWD-5240.
Page 1 of 4
IWA-5244, "Buried Components" (b) For buried components where a VT-2 visual examination cannot be performed, the examination requirement is satisfied by the following:
(1)The system pressure test for buried components that are isolable by means of valves shall consist of a test that determines the rate of pressure loss. Alternatively, the test may determine the change in flow between the ends of the buried components.
The acceptable rate of pressure loss of flow shall be established by the Owner.
(2)The system pressure test for nonisolable buried components shall consist of a test to confirm that flow during operation is not impaired.
(3)Test personnel need not be qualified for VT-2 visual examination.
Examination Category D-B, Item No. D2.10. The extent of examination for the system leakage test (IWD-5221) of pressure retaining components is the pressure retaining boundary.
IWD-5240, "Boundaries" (a)The pressure retaining boundary includes only those portions of the system required to operate or support the safety function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required.
(b) Items outside the boundaries of IWD-5240(a), and open ended discharge piping, are excluded from the examination requirements.
Reason for Request
The buried piping in question consists of about 90 feet of 30-inch diameter cast steel piping located between the Circulating Water Pump House and the Turbine Building.
These piping sections are buried approximately seven feet underground with a road built over it. There is no access to this buried piping other than excavation. No annulus was provided during original construction that would allow for testing or examination of these buried sections of piping. It is not possible to perform a direct VT-2 examination when performing a system leakage test in accordance with IWA-521 1.
An alternative to the IWA-5211 system leakage test is to isolate the buried sections of the piping and perform a test that determines the rate of pressure loss. This test method is a stated method in ASME Section Xl, 1998 Edition, 2000 Addenda, IWA-5244(b)(1). The existing isolation valves available to isolate this buried portion of piping are six butterfly valves, three per piping section. 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 a test in accordance with IWA-5244(b)(1), as it would be necessary to either replace the valves with those of better leakage characteristics or install temporary blind flanges to conduct this test.
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Such a test methodology would be difficult to perform and would remove one train of service water. This would also require entry into a dual unit, seven-day TSAC, as described below.
The SW system for both units is configured with a ring header such that both sides (i.e., north and south headers) of the system are supplying both units. PBNP TS 3.7.8 requires, "SW ring header continuous flowpath not interrupted" for SW system operability. Removing one section of the ring header from service reduces the redundancy of the system. Ifthe 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 one hour in accordance with TSAC 3.7.8.C, Required Action C.1. Isolating a section of the SW ring header also requires entry into a dual unit TSAC to restore the flowpath within seven days.
The 1998 Edition, 2000 Addenda, IWA-5244(b)(1), 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 physically configured to make this determination. To use an ultrasonic flow meter would require a length of straight pipe 15 times its diameter.
PBNP plant experience has shown that 15 pipe diameters of straight length piping are the minimum length required in order to get an accurate rate of flow. As-built drawings of the system show a 12-foot, 3-inch straight length of piping with a 24-inch by 30-inch reducer. Therefore, the ultrasonic gauge would require a 30-foot length of straight piping without turbulence-inducing components to work correctly. The configuration of the SW system will not allow for determining the change in flow between the ends of the buried piping.
NMC recognizes that Microbiologically Influenced Corrosion (MIC) could be a concern for the SW piping, as it contains lake water. However, NMC has determined that the possibility of erosion from MIC in these sections of piping is minimal. This is due to the continuous high flow rate of water through the piping, which does not support significant microbiological attack.
Proposed Alternative and Basis for Use The proposed test methodology will confirm unimpaired flow as stated in ASME Section Xl, 1998 Edition, 2000 Addenda IWA-5244(b)(2):
"The system pressure test for nonisolable buried components shall consist of a test to confirm that flow during operation is not impaired."
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NMC proposes the use of the following PBNP Inservice Testing procedures conducted on a quarterly basis to verify adequate flow through the SW system during operation:
IT-7A, "P-32A Service Water Pump (Quarterly)"
IT-78, "P-32B Service Water Pump (Quarterly)"
IT-7C, "P-32C Service Water Pump (Quarterly)"
IT-7D, "P-32D Service Water Pump (Quarterly)"
IT-7E, "P-32E Service Water Pump (Quarterly)"
IT-7F, "P-32F Service Water Pump (Quarterly)"
The buried portions of piping are isolable to protect against a header break but not sufficiently isolable for a pressure test. Application of IWA-5244(b)(2) will provide an adequate level of quality and safety. The use of the inservice pump tests 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 failed inservice pump tests for three of six SW pumps providing flow to this portion of buried pipe. This failure would result in a 72-hour TSAC 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 fourth inservice interval, which began on July 1,2002 and is scheduled to end on June 30, 2012.
References ASME Section Xl, 1998 Edition with Addenda through 2000 EPRI TM-1001, Microbiologically Influenced Corrosion PBNP Technical Specification 3.7.8, Service Water (SW) System Page 4 of 4