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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities NG-24-0004, 2023 Annual Radiological Environmental Operating Report2024-05-0808 May 2024 2023 Annual Radiological Environmental Operating Report NG-24-0003, Submittal of 2023 Annual Radioactive Material Release Report2024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Material Release Report ML24072A0292024-03-29029 March 2024 Nextera Energy Duane Arnold, Llc. Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) NG-24-0002, 2023 Annual Exposure Report - Form 5s2024-03-0606 March 2024 2023 Annual Exposure Report - Form 5s NG-24-0001, 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update2024-03-0606 March 2024 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update 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) NG-23-0010, Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-12-0606 December 2023 Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0009, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment NG-23-0006, Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-05-23023 May 2023 Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update ML23137A1672023-05-11011 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report NG-23-0004, 2022 Annual Radioactive Material Release Report2023-04-25025 April 2023 2022 Annual Radioactive Material Release Report NG-23-0003, 2022 Annual Exposure Report - Form 5s2023-04-21021 April 2023 2022 Annual Exposure Report - Form 5s NG-23-0001, 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report2023-03-27027 March 2023 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML22339A0012022-12-22022 December 2022 Acceptance of Requested Licensing Action Amendment Request for Common Emergency Plan IR 05000331/20220032022-12-13013 December 2022 NRC Inspection Report No. 05000331/2022003 (Drss) ML22285A0072022-10-13013 October 2022 NRC Analysis of NextEra Energy Duane Arnold'S Decommissioning Funding Status Report, Docket No. 50-331 IR 05000331/20220022022-07-13013 July 2022 NRC Inspection Report Nos. 05000331/2022002(DNMS) and 07200032/2022002(DNMS) ML22090A1922022-05-26026 May 2022 Letter to B. Coffey, FPL from M. Doell - Duane Arnold Post Shutdown Activities Report Review Letter ML22132A2872022-05-24024 May 2022 ISFSI DQAP Approval Letter ML22111A0332022-05-20020 May 2022 Operating License Page Correction Letter to B. Coffey, Florida Power and Light, from M. Doell NG-22-0055, Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan2022-05-20020 May 2022 Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan ML22089A0492022-05-12012 May 2022 Sfmp Review Letter NG-22-0053, 2021 Annual Radiological Environmental Operating Report2022-05-0606 May 2022 2021 Annual Radiological Environmental Operating Report NG-22-0052, Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative2022-05-0404 May 2022 Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative IR 05000331/20224012022-04-27027 April 2022 Decommissioning Security Inspection Report 05000331/2022401 NG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 02022-04-26026 April 2022 Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0 NG-22-0049, 2021 Annual Radioactive Material Release Report2022-04-26026 April 2022 2021 Annual Radioactive Material Release Report ML22066A7632022-04-25025 April 2022 ISFSI-Only Emergency Plan License Amendment Approval L-2022-068, NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 22022-04-25025 April 2022 NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 2 NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 02022-04-13013 April 2022 Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 0 NG-22-0047, Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2022-04-11011 April 2022 Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool NG-22-0042, Registration of Independent Spent Fuel Installation Storage Casks2022-04-0808 April 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0041, and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report2022-03-31031 March 2022 and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s ML22080A1822022-03-22022 March 2022 Letter to B. Coffey from M. Doell - Duane Arnold ISFSI QAPD RAI Letter L-2022-012, Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3)2022-03-16016 March 2022 Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML22059A7462022-03-10010 March 2022 ISFSI-Only Physical Security Plan License Amendment Approval NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022 Registration of Independent Spent Fuel Installation Storage Casks IR 05000331/20220012022-03-0404 March 2022 Subject: NRC Inspection Report Nos. 05000331/2022001(DNMS) and 07200032/2022001(DNMS) 2024-09-04
[Table view] Category:Safety Evaluation
MONTHYEARML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter ML22132A2872022-05-24024 May 2022 ISFSI DQAP Approval Letter ML22089A0492022-05-12012 May 2022 Sfmp Review Letter ML22066A7632022-04-25025 April 2022 ISFSI-Only Emergency Plan License Amendment Approval ML22028A2822022-02-0303 February 2022 Defueled Physical Security Plan License Amendment Approval ML21067A6422021-05-13013 May 2021 Cyber Security License Amendment Approval ML21098A1662021-04-28028 April 2021 PDEP and EAL License Amendment Approval ML21097A1412021-04-13013 April 2021 EP Exemption Issuance Letter and SE ML20225A0002020-08-27027 August 2020 Approval of Quality Assurance Topical Report (FPL-3), Revision 0 (EPID-L-2020-LLQ-0002) ML20184A0032020-07-30030 July 2020 Issuance of Amendment No. 312 Removal of License Condition 2.C.(3), Fire Protection Program ML20134J1042020-07-10010 July 2020 Issuance of Amendment No. 311 to Revise Operating License and Technical Specifications for Permanently Defueled Conditions ML20083G0082020-04-29029 April 2020 Issuance of Amendment No. 310 Changes to the Post-Shutdown Emergency Plan for Duane Arnold Energy Center ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19310C2042020-01-0202 January 2020 Issuance of Amendment No. 309 to Align Technical Specifications Staffing and Administrative Requirements ML19204A2872019-08-28028 August 2019 Approval of a Certified Fuel Handler Training and Retraining Program ML19198A0102019-07-23023 July 2019 Approval of Change in the BWRVIP Integrated Surveillance Program Capsule Test Schedule to Accommodate Early Closure ML19168A1302019-06-21021 June 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4391; EPID No. L-2014-JLD-0039) ML18292A5662018-11-30030 November 2018 Issuance of Amendment 308 to Upgrade Emergency Action Level Scheme for Duane Arnold Energy Center (DAEC) ML18241A3832018-10-31031 October 2018 Issuance of Amendment 307 to Revise Technical Specifications to Adopt TSTF-551, Revision 3 ML18179A1842018-08-16016 August 2018 Issuance of Amendment 306 to Revise Technical Specification 3.5.1, ECCS-Operating ML18192C1832018-07-24024 July 2018 Fifth 10-Year Inservice Relief Request RR-05 ML18145A1942018-06-15015 June 2018 Relief Request No. NDE R017 Fourth Inservice Inspection Interval Duane Arnold Energycenter (EPID-L-2017-LLR-0135) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18053A2092018-04-16016 April 2018 Request for Relief No. 03 Proposed Use of Alternative Requirements for Nozzle Inner Radius and Nozzle-to-Shell Weld Inspection for Fifth Inservice Inspection Interval (CAC No. MF9374; EPID L-2017-LLR-0110) ML18016A6272018-03-0909 March 2018 Issuance of License Amendment No. 304 Revision to Technical Specification 3.1.2, Reactor Anomalies ML18011A0592018-03-0707 March 2018 Issuance of License Amendment No. 303 Revision to Technical Specification Table 3.3.2.1-1, Control Rod Block Instrumentation ML17353A6822018-01-19019 January 2018 Request for Relief No. RR 01, Regarding Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds for the Renewed Operating License Term ML17347A1112018-01-17017 January 2018 Safety Evaluation for Request for Relief from Seal Weld Procedure Qualification, Relief Request No. RR-04 ML17272A0182017-12-19019 December 2017 Relief Request No. RR-02- Proposed Alternative to ASME Code Examination Requirements for Buried Piping Related to Fifth Inservice Inspection Interval Program Plan ML17212A6462017-10-18018 October 2017 Issuance of Amendment to Modify the Plume Exposure Pathway Emergency Planning Zone Boundary ML17220A0262017-09-21021 September 2017 Issuance of Amendment 301 to Revise Emergency Plan ML17129A0372017-05-26026 May 2017 Safety Evaluation Regarding Implementation of Mitigation Strategies and Reliable Spent Fuel Pool Instrument Related to Orders EA-12-049 and EA-12-051 ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17072A2322017-03-30030 March 2017 Issuance of Amendment to Revise Technical Specifications Fuel Storage Requirements ML16313A4752016-11-30030 November 2016 Correction of Errors in Safety Evaluation Associated with License Amendment No. 298 ML16263A2452016-10-17017 October 2016 Issuance of Amendment to Technical Specifications Section 5.5.6 for the Inservice Testing Program ML16211A5142016-09-12012 September 2016 Issuance of Amendment to Revise Technical Specifications 2.1.1.2, Safety Limit Minimum Critical Power Ratio ML16210A0082016-08-30030 August 2016 Issuance of Amendment to Extend Containment Leakage Test Frequency ML16153A0912016-08-18018 August 2016 Issuance of Amendment to Revise the Value of Reactor Steam Dome Pressure ML16180A0862016-07-25025 July 2016 Issuance of Amendment to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report ML16174A2812016-07-13013 July 2016 Issuance of Amendment (TSCR-154) to Correct Examples in Technical Specifications Section 1.4, Frequency ML16053A4262016-04-29029 April 2016 Correction of Typographical Errors in Safety Evaluation Associated with License Amendment No. 292 ML16008A0862016-01-21021 January 2016 Relief Request No. PR-01, PR-02, VR-01, VR-02, and VR-03 Related to the Inservice Testing Program for the Fifth 10-Year Interval ML15310A0822015-12-22022 December 2015 Issuance of Amendment to Adopt Technical Specifications Task Force (TSTF)-501, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML15169A2612015-08-18018 August 2015 Issuance of Amendment Concerning Extension of Cyber Security Plan Milestone 8 Completion Date ML15014A2002015-02-10010 February 2015 Issuance of Amendment to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523 Generic Letter 2008-01, Managing Gas Accumulation (Tac No. MF4358) ML14144A0022014-06-0909 June 2014 Relief Request No. VR-03 Related to the Inservice Testing Program for the Fourth 10-Year Interval ML14099A3352014-04-29029 April 2014 Relief for 2nd Period Limited Weld Examinations ML13301A7052013-11-27027 November 2013 Issuance of Amendment Adopting TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. ML13323B4432013-11-26026 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation 2024-06-12
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Text
March 14, 2007 Mr. Gary Van Middlesworth Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785
SUBJECT:
SAFETY EVALUATION OF RELIEF REQUEST FOR THE DUANE ARNOLD ENERGY CENTER FOURTH 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. MD1844)
Dear Mr. Van Middlesworth:
By letter dated May 8, 2006, as supplemented on November 3, 2006, FPL Energy Duane Arnold, LLC (FPL Energy) submitted a request for relief (designated as PR-03) from the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) requirements for the Duane Arnold Energy Center (DAEC).
The subject relief request is for the fourth 10-year inservice testing (IST) interval at DAEC, which began on February 1, 2006.
The U.S. Nuclear Regulatory Commission staff has completed its review of relief request PR-03 as documented in the enclosed Safety Evaluation (SE). Our SE concludes that the proposed alternative provides reasonable assurance of the operational readiness of the standby liquid control pumps. Therefore, the proposed alternative is authorized, pursuant to Section 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations for the remainder of the fourth 10-year IST interval, on the basis that compliance with the ASME OM Code requirements would result in hardship without a compensating increase in the level of quality and safety.
If you have any questions regarding this matter, please contact Mr. Karl Feintuch at (301) 415-3079.
Sincerely,
/RA/
L. Raghavan, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
Safety Evaluation cc w/encl: See next page
ML070160009 OFFICE LPL3-1/PM LPL3-1/PM LPL3-1/LA CPTB/BC OGC LPL3-1/BC NAME KFeintuch REnnis THarris JMcHale TCampbell LRaghavan DATE 3/12/07 1/19/07 3/9/07 1/29/07 2/1/07 3/14/07 Duane Arnold Energy Center cc:
Mr. J. A. Stall Mr. M. Warner Senior Vice President, Nuclear and Vice President, Nuclear Operations Chief Nuclear Officer Support Florida Power & Light Company Florida Power & Light Company P. O. Box 14000 P. O. Box 14000 Juno Beach, FL 33408-0420 Juno Beach, FL 33408-0420 Mr. M. S. Ross Mr. D. A. Curtland Managing Attorney Plant Manager Florida Power & Light Company Duane Arnold Energy Center P. O. Box 14000 3277 DAEC Rd.
Juno Beach, FL 33408-0420 Palo, IA 52324-9785 Mr. R. E. Helfrich Mr. R. S. Kundalkar Senior Attorney Vice President, Nuclear Engineering Florida Power & Light Company Florida Power & Light Company P. O. Box 14000 P. O. Box 14000 Juno Beach, FL 33408-0420 Juno Beach, FL 33408-0420 Mr. W. E. Webster Daniel K. McGhee Vice President, Nuclear Operations Iowa Department of Public Health Florida Power & Light Company Bureau of Radiological Health P. O. Box 14000 321 East 12th Street Juno Beach, FL 33408-0420 Lucas State Office Building, 5th Floor Des Moines, IA 50319-0075 John Bjorseth Site Director Chairman, Linn County Duane Arnold Energy Center Board of Supervisors 3277 DAEC Road 930 1st Street SW Palo, IA 52324 Cedar Rapids, IA 52404 Steven R. Catron Manager, Regulatory Affairs Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 U. S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1 Palo, IA 52324 October 12, 2006 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO A RELIEF REQUEST FOR THE FOURTH 10-YEAR INTERVAL OF THE INSERVICE TESTING PROGRAM FPL ENERGY DUANE ARNOLD, LLC DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331
1.0 INTRODUCTION
By letter dated May 8, 2006, FPL Energy Duane Arnold, the licensee for Duane Arnold Energy Center (DAEC), requested relief from certain inservice testing (IST) requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the Standby Liquid Control (SBLC) injection pumps.
By letter dated November 3, 2006, the licensee provided additional information related to relief request PR-03.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, requires that IST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed at 120-month (10-year) IST program intervals in accordance with the specified ASME Code and applicable addenda incorporated by reference in the regulations, except where alternatives have been authorized or relief has been requested by the licensee and granted by the Nuclear Regulatory Commission (NRC) pursuant to paragraphs (a)(3)(i), (a)(3)(ii), or (f)(6)(i) of 10 CFR 50.55a.
In accordance with 10 CFR 50.55a(f)(4)(ii), licensees are required to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in the regulations 12 months prior to the start of each 120-month IST program interval. In accordance with 50.55a(f)(4)(iv), IST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b),
subject to NRC approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met.
In proposing alternatives or requesting relief, the licensee must demonstrate that: (1) the proposed alternatives provide an acceptable level of quality and safety; (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety; or (3) conformance is impractical for the facility.
ENCLOSURE
Section 50.55a authorizes the NRC to approve alternatives and to grant relief from ASME Code requirements upon making necessary findings. NRC guidance contained in Generic Letter (GL) 89-04, Guidance on Developing Acceptable Inservice Testing Programs, provides alternatives to Code requirements which are acceptable. Further guidance is given in GL 89-04, Supplement 1, and NUREG-1482, Revision 1, Guidance for Inservice Testing at Nuclear Power Plants.
At DAEC, the code of record for the fourth 10-year interval is the 2001 Edition through 2003 Addenda of the ASME OM Code.
3.0 TECHNICAL EVALUATION
3.1 Pump Relief Request PR-03 3.1.1 Code Requirements The licensee requested relief from ISTB-3550 and ISTB-5300(a)(1) of the ASME OM Code.
Paragraph ISTB-3550 requires that when measuring flow rate, a rate or quantity meter shall be installed in the pump test circuit.
Paragraph ISTB-5300(a)(1) requires that for the Group A test and the comprehensive test, after pump conditions are as stable as the system permits, each pump shall be run at least 2 minutes. At the end of this time at least one measurement or determination of each of the quantities required by Table ISTB-3000-1 shall be made and recorded.
Relief was requested for the 1P230A and 1P230B SBLC pumps.
3.1.2 Licensees Basis for Requesting Relief In its letter dated May 8, 2006, the licensee stated:
Impracticality of Compliance The positive displacement SBLC pumps are designed to pump a constant flow rate regardless of system resistance. The SBLC system was not designed with a flow meter in the flow loop. The system was designed with a test tank, where the change in the level can be measured over time and a flow rate calculated. As part of the modifications made to the SBLC system for the ATWS Rule (10 CFR 50.62), DAEC installed instrumentation to measure flow. The ultrasonic flow meter that was installed, however, was not intended to meet the accuracy requirements of the ASME OM Code, and has not proven to be capable of meeting Code accuracy requirements. The accuracy performance of the flow meter is attributed to the lack of adequate straight length of pipe to establish fully developed flow.
In March, 2006, portable ultrasonic flow meters were installed on the common SBLC pump discharge piping to determine the practicality of using later-technology ultrasonic flow meters to measure flow per ASME OM Code requirements. The flow meter transducers were installed at three different locations on the discharge piping. A vendor
representative was on-site to facilitate proper installation and setup of the transducers and flow meters. Each location produced significantly different measured flow rates compared to the other locations and the test tank level method.
NUREG 1842, Revision 1 recognizes that plants may have difficulties with flow instrumentation. In Section 2.5.1, Justification for Relief, the NUREG states that compliance with the Code may be impractical because of design limitations. Imposition of the Code requirements would require significant system redesign and modifications.
For example, a flow meter does not meet the accuracy requirements of ISTB 3510
[4.7.1.] and Table ISTB 3500-1 [4.7.1-1] because the present system configuration does not have a straight section of pipe of sufficient length in which to measure flow accurately ... .
Burden Caused by Compliance Flow measurement cannot be achieved to the required accuracy using a flow meter.
In addition, the SBLC test tank is not large enough to provide two minutes of flow prior to recording flow data. As discussed in NUREG 1482, Revision 1, Section 5.5.2, requiring installation of a flow meter to measure the flow rate, and to guarantee the test tank size, such that the pump flow rate will stabilize in 2 minutes before recording data, would be a burden because of the design and installation changes that would have to be made to the existing system.
3.1.3 Licensees Proposed Alternative Testing In its letter dated May 8, 2006, the licensee stated:
Flow rate for the SBLC pumps will be determined by measuring the change in test tank level over time. The pump will be started with suction from the test tank and will discharge to storage barrels. The test tank level will be approximately the same at the beginning of each test to ensure repeatability. After at least two minutes of pump operation and a change of tank level of at least 20 inches, the time and level are recorded and the pump stopped. The change in level over the measured time will be converted to flow rate by the following formula:
Q (GPM) = L (inch) / t (second)
Where: Q is flow rate is a constant which reflects tank dimensions and unit conversions L is the measured change in level in the tank in time t Pump discharge pressure will match system pressure up to the shutoff head of the positive displacement pump. Because of the characteristics of a positive displacement pump, there should be virtually no change in pump discharge flow rate as a result of the rising level in the temporary storage barrels. Therefore, increasing level will not have an impact on test results. By having approximately the same level in the tank at the beginning of each test, repeatable results can be achieved.
Per NUREG 1482, Revision 1, Section 5.5.2, Use of Tank Level to Calculate Flow Rate for Positive Displacement Pumps, when flow meters are not installed in the flow loop of a system with a positive displacement pump, it is impractical to
directly measure flow rate for the pump. The staff has determined that, if the licensee uses the tank level to calculate the flow rate as described in Subsection ISTB 3550 [4.7.5], the implementing procedure must include the calculation method and any test conditions needed to achieve the required accuracy. ... If the meter does not directly indicate the flow rate, the record of the test shall identify the method used to reduce the flow data. The test tank level will be measured in accordance with the accuracy requirement of OM Code Table ISTB-3500-1. The calculation method and test conditions required to achieve this accuracy are documented in the implementing procedures.
3.1.4 Evaluation The ASME OM Code requires that pump flow rate be measured in order to determine the extent of any pump degradation. A 2-minute run time is required by the ASME OM Code in order to achieve stable pump performance parameters before data are recorded during the test.
The positive displacement SBLC pumps utilized at DAEC are designed to pump a constant flow rate regardless of system resistance. The SBLC system was not initially designed with flow meter instrumentation in the flow loop, and uses a test tank to determine flow rate by measuring the change in tank level over a period of time. As part of the modifications made to the SBLC system to meet 10 CFR 50.62 requirements, DAEC installed an ultrasonic flow meter to measure SBLC flow. However, the ultrasonic flow meter was not intended to meet the accuracy requirements of the ASME OM Code, and has not proven to be capable of meeting OM Code accuracy requirements due to the lack of an adequate straight length of pipe which is necessary to establish fully developed flow.
In March 2006, DAEC installed portable ultrasonic flow meters to determine the practicality of using later technology instrumentation to measure flow per ASME OM Code requirements. The portable ultrasonic flow meters failed to produce consistent results using tank level to calculate flow rate (the remaining practical alternative). However, the test tank is not large enough to provide 2 minutes of flow prior to recording flow data. Requiring DAEC to install a larger test tank to facilitate pump testing would be a burden because of the design, fabrication, and installation changes that would have to be made.
As an alternative to the ASME OM Code requirements, the licensee is proposing to measure the flow rate by determining the change in source tank level over a period of time and calculating an average flow rate from the tank. The change in flow resistance due to the rising level of temporary storage barrels, will be small in comparison with the pump discharge pressure, thereby having no significant effect on the test results. Provided the tank level at the beginning of each test is approximately the same, repeatable results can be achieved. This method is consistent with the NRC Staffs recommendation in NUREG-1482, Revision 1, and therefore provides reasonable assurance of the pumps operational readiness when the test tank level is measured in accordance with the accuracy requirements of Table ISTB-3500-1.
Implementing procedures must include the calculation method and any test conditions required to achieve this accuracy.
4.0 CONCLUSION
The NRC staff concludes that the proposed alternative provides reasonable assurance of the operational readiness of the SBLC pumps. Therefore, the proposed alternative is authorized, pursuant to 10 CFR 50.55a(a)(3)(ii) for the remainder of the fourth 10-year IST interval, on the basis that compliance with the ASME OM code requirements would result in hardship without a compensating increase in the level of quality and safety.
Principal Contributor: Y. Wong Date: March 14, 2007