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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24303A3582024-10-25025 October 2024 Steam Generator Tube Inservice Inspection Discussion-Fall 2024 (Oct. 25, 2024) L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-016, Twenty-Eighth Refueling Outage Inservice Inspection Summary Report2023-02-21021 February 2023 Twenty-Eighth Refueling Outage Inservice Inspection Summary Report L-22-100, 180-Day Steam Generator Tube Inspection Report2022-05-0505 May 2022 180-Day Steam Generator Tube Inspection Report L-22-015, Twenty-Second Refueling Outage Inservice Inspection Summary Report2022-02-0707 February 2022 Twenty-Second Refueling Outage Inservice Inspection Summary Report L-21-191, Twenty-Seventh Refueling Outage Inservice Inspection Summary Report2021-08-0303 August 2021 Twenty-Seventh Refueling Outage Inservice Inspection Summary Report L-21-034, Report of Facility Changes, Tests and Experiments2021-02-23023 February 2021 Report of Facility Changes, Tests and Experiments L-20-264, 180-Day Steam Generator Tube Inspection Report2020-10-13013 October 2020 180-Day Steam Generator Tube Inspection Report L-20-156, Steam Generator Inspection Reports - Spring 2020 Refueling Outage2020-07-28028 July 2020 Steam Generator Inspection Reports - Spring 2020 Refueling Outage L-20-127, Supplement to 10 CFR 50.55a Request Number VRR4, Revision 0, Containment Isolation Valve Test Frequency2020-04-0606 April 2020 Supplement to 10 CFR 50.55a Request Number VRR4, Revision 0, Containment Isolation Valve Test Frequency L-20-019, Twenty-Sixth Refueling Outage Inservice Inspection Summary Report2020-01-20020 January 2020 Twenty-Sixth Refueling Outage Inservice Inspection Summary Report L-19-107, Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2019-08-27027 August 2019 Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-19-060, Attachment C: Beaver Valley, Unit 2, 2R20 Steam Generator Examination Results 2RCS-SG21C (Tubes with Service Induced Indications)2019-03-28028 March 2019 Attachment C: Beaver Valley, Unit 2, 2R20 Steam Generator Examination Results 2RCS-SG21C (Tubes with Service Induced Indications) L-19-034, Steam Generator Inspection Reports - Fall 2018 Refueling Outage2019-01-31031 January 2019 Steam Generator Inspection Reports - Fall 2018 Refueling Outage ML19031B5572019-01-31031 January 2019 Twentieth Refueling Outage Inservice Inspection Summary Report L-18-176, Twenty-Fifth Refueling Outage Inservice Inspection Summary Report2018-07-23023 July 2018 Twenty-Fifth Refueling Outage Inservice Inspection Summary Report L-18-107, Submittal of Snubber Program for Beaver Valley Power Station, Units Nos. 1 and 22018-06-0707 June 2018 Submittal of Snubber Program for Beaver Valley Power Station, Units Nos. 1 and 2 L-17-294, Submittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22017-10-17017 October 2017 Submittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 L-17-298, Submittal of the 10-Year Interval Inservice Testing Programs2017-10-10010 October 2017 Submittal of the 10-Year Interval Inservice Testing Programs CNS-17-044, Inservice Inspection Report for Unit 1 End of Cycle 23 Refueling Outage2017-08-21021 August 2017 Inservice Inspection Report for Unit 1 End of Cycle 23 Refueling Outage L-17-240, Nineteenth Refueling Outage Lnservice Inspection Summary Report2017-08-18018 August 2017 Nineteenth Refueling Outage Lnservice Inspection Summary Report L-17-074, Steam Generator Inspection Reports - Spring 2017 Refueling Outage2017-08-0808 August 2017 Steam Generator Inspection Reports - Spring 2017 Refueling Outage ML17013A5872017-01-13013 January 2017 Twenty-Fourth Refueling Outage Inspection Summary Report L-16-241, Updated Steam Generator Inspection Report - Fall 2015 Refueling Outage2016-10-11011 October 2016 Updated Steam Generator Inspection Report - Fall 2015 Refueling Outage L-16-022, Steam Generator Inspection Reports - Fall 2015 Refueling Outage2016-01-22022 January 2016 Steam Generator Inspection Reports - Fall 2015 Refueling Outage L-16-019, Eighteenth Refueling Outage Lnservice Inspection Summary Report2016-01-22022 January 2016 Eighteenth Refueling Outage Lnservice Inspection Summary Report L-15-200, Twenty-Third Refueling Outage Inservice Inspection Report2015-08-18018 August 2015 Twenty-Third Refueling Outage Inservice Inspection Report L-14-243, Seventeenth Refueling Outage Inservice Inspection Summary Report2014-08-20020 August 2014 Seventeenth Refueling Outage Inservice Inspection Summary Report ML14034A1082014-01-30030 January 2014 Twenty-Second Refueling Outage Inservice Inspection Report L-13-058, Steam Generator Inspection Report - Technical Specification 5.6.6.2.12013-04-23023 April 2013 Steam Generator Inspection Report - Technical Specification 5.6.6.2.1 L-13-027, Sixteenth Refueling Outage Inservice Inspection Summary Report2013-02-0101 February 2013 Sixteenth Refueling Outage Inservice Inspection Summary Report L-12-419, Submittal of Twenty-First Refueling Outage Inservice Inspection Report Revision2012-12-28028 December 2012 Submittal of Twenty-First Refueling Outage Inservice Inspection Report Revision L-12-206, Twenty-First Refueling Outage Inservice Inspection Report2012-08-0808 August 2012 Twenty-First Refueling Outage Inservice Inspection Report L-11-182, Fifteenth Refueling Outage Inservice Inspection Report2011-07-0505 July 2011 Fifteenth Refueling Outage Inservice Inspection Report L-11-002, Twentieth Refueling Outage Inservice Inspection Report2011-01-31031 January 2011 Twentieth Refueling Outage Inservice Inspection Report L-10-020, Fourteenth Refueling Outage Inservice Inspection Report2010-02-22022 February 2010 Fourteenth Refueling Outage Inservice Inspection Report L-09-203, Nineteenth Refueling Outage Inservice Inspection Report for April 1, 2008 to May 21, 20092009-08-18018 August 2009 Nineteenth Refueling Outage Inservice Inspection Report for April 1, 2008 to May 21, 2009 L-08-339, Impractical American Society of Mechanical Engineers Code Section XI Weld Examination Requirements2008-11-26026 November 2008 Impractical American Society of Mechanical Engineers Code Section XI Weld Examination Requirements L-08-265, Thirteenth Refueling Outage Inservice Inspection Report2008-08-18018 August 2008 Thirteenth Refueling Outage Inservice Inspection Report ML0802500602008-01-21021 January 2008 Eighteenth Refueling Outage Inservice Inspection Report L-07-147, Supplemental Information in Support of ASME Code Relief Request PRR62007-11-14014 November 2007 Supplemental Information in Support of ASME Code Relief Request PRR6 ML0713703472007-05-11011 May 2007 Proposed Alternatives and Relief Requests Associated with the Inservice Testing Program Ten-Year Update L-07-023, Twelfth Refueling Outage Inservice Inspection Report2007-02-0202 February 2007 Twelfth Refueling Outage Inservice Inspection Report L-06-104, Seventeenth Refueling Outage Inservice Inspection Report2006-07-14014 July 2006 Seventeenth Refueling Outage Inservice Inspection Report L-05-164, Proposed Alternative to American Society of Mechanical Engineers Code Section XI Visual Examination Requirements Associated with Third Ten-Year Interval Inservice Inspection Program2005-10-31031 October 2005 Proposed Alternative to American Society of Mechanical Engineers Code Section XI Visual Examination Requirements Associated with Third Ten-Year Interval Inservice Inspection Program L-05-030, Sixteenth Refueling Outage Inservice Inspection Report2005-02-10010 February 2005 Sixteenth Refueling Outage Inservice Inspection Report L-05-014, Inservice Testing Programs, Proposed Revisions 1M and 2J2005-02-0404 February 2005 Inservice Testing Programs, Proposed Revisions 1M and 2J L-04-117, Inservice Testing Program, Proposed Revision 1L2004-09-0303 September 2004 Inservice Testing Program, Proposed Revision 1L L-04-100, No. 2, Inservice Testing Programs, Proposed Revisions 1K and 2I, Addenda 12004-07-0909 July 2004 No. 2, Inservice Testing Programs, Proposed Revisions 1K and 2I, Addenda 1 2024-09-17
[Table view] Category:Letter type:L
MONTHYEARL-24-254, Cycle 25 Core Operating Limits Report2024-11-15015 November 2024 Cycle 25 Core Operating Limits Report L-24-246, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-10-21021 October 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-223, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-09-26026 September 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-198, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0707 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-23-241, Submittal of the Updated Final Safety Analysis Report, Revision 272023-11-29029 November 2023 Submittal of the Updated Final Safety Analysis Report, Revision 27 L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report 2024-09-26
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FENOC FENOCRoute Beaver Valley Power Station 168 SRPO. Box 4 FirstEnergyNuclearOperating Company Shippingport,PA 15077-0004 Mark B. Bezilla 724-682-5234 Site Vice President Fax: 724-643-8069 July 8, 2002 L-02-063 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Inservice Inspection Program, Proposed Revision 11 Attached for NRC review and approval is proposed Revision 11 to the Beaver Valley Power Station Unit 1 (BVPS-1) Inservice Testing (IST) Program. This revision incorporates a new relief request, Pump Relief Request No. 6 (PRR6), which is being submitted for NRC review and approval in accordance with 10 CFR 50.55a(a)(3)(i).
The BVPS-1 Boric Acid Transfer Pumps [lCH-P-2A and 2B] are currently tested on a quarterly frequency through a mini-flow recirculation line without measuring flow, and on a refueling frequency through a full-flow recirculation line while all required parameters are measured. This testing is in accordance with Position 9 of Generic Letter 89-04 and is documented in the current Pump Refueling Outage Justification No. 1 (PROJI).
PRR6 requests that as an alternative to the testing performed, the full-flow recirculation test be performed while on-line just prior to a refueling outage. Full-flow testing at this frequency will assist in our desire to minimize refueling outage durations and maximize work management, while not impacting the level of quality and safety of the Boric Acid Transfer Pumps.
Relief is needed because the ASME XI Code does not recognize testing on-line at any frequency other than quarterly. PRR6 provides the basis for why this alternative testing is acceptable. NRC approval of PRR6 is requested by February 8, 2003, in order to incorporate this planned testing prior to the BVPS-1 Fifteenth Refueling Outage currently scheduled to begin on March 8, 2003.
If you have any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Affairs/Corrective Action at 724-682-5284.
Sincerely, Mark B. Bezi
Beaver Valley Power Station, Unit No. 1 Inservice Inspection Program, Proposed Revision 11 L-02-063 Page 2 Enclosure c: Mr. D. S. Collins, NRR Project Manager Mr. D. M. Kern, NRC Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator
BEAVER VALLEY POWER STATION Unit 1 Inservice Testing (IST) Program For Pumps And Valves Proposed Revision 11 Preparer 5.7 ** q. Date:
IQR/OSC Meeting # Date:
Owner Approval Date: .
Approval Authority 0. Date:
BV-1 Inservice Test Program Proposed Revision 1I PUMP RELIEF REQUEST 6 Pump Asset No(s): 1CH-P-2A 1CH-P-2B System: 7 - Chemical and Volume Control Function: To supply borated water from the Boric Acid Tanks to the suction of the Charging HHSI pump for injection into the RCS for emergency boration.
Test Requirement: Per OM-6, Paragraph 5.2, "Test Procedure" and Table 2, "Inservice Test Parameters," flow rate shall be determined and recorded.
Basis for Relief: In accordance with 10CFR50.55a(a)(3)(i), relief is requested on the basis that the proposed alternatives would provide an acceptable level of quality and safety.
Testing the Boric Acid Transfer pumps using the emergency boration flow path is impractical during power operation because it would inject water with higher concentration of boric acid into the RCS which would result in a reactivity transient and subsequent reactor shutdown. Therefore, the code-required quarterly testing is performed using an alternate test loop as shown on the attached figure. During normal plant operations, the pumps are tested quarterly through [RO-1CH-ORBA-1 (2)], the restricting orifices in the minimum flow fixed resistance recirculation lines. However, there are no installed flow instruments in these recirculation lines. Because of the restricting orifices, the flow is assumed to be fixed and at its reference value. Delta-P and vibration are then measured and compared to the acceptance criteria. Position 9 of GL 89-04 states that "In cases where flow can only be established through a non instrumented minimum flow path during quarterly pump testing and a path exists at cold shutdowns or refueling outages to perform a test of the pump under full or substantial flow conditions, the staff has determined that the increased interval is an acceptable alternative to the Code requirements, provided that pump differential pressure, flow rate, and bearing vibration measurements are taken during this testing and that quarterly testing also measuring at least pump differential pressure and vibration is continued."
Therefore, in accordance with Position 9 of the GL 89-04, the pumps have also been tested through their full flow recirculation flow paths through [HCV 1CH- 110(105)], at a refueling frequency. For the full-flow recirc test, the flow is measured using a portable ultrasonic flow meter that has been "wet-flow" calibrated to within the +/-2% accuracy required by ASME. In order to install the flow meters, however, the insulation on the piping must be removed and the heat trace elements must be moved away from where the transducers and tracks will be installed. Moving the heat trace elements places stresses on them, which increases the probability of failure of the heat trace elements. The heat tracing on the boric acid piping is needed to support system operability.
Therefore, it is also impractical to test the pumps at a cold shutdown frequency.
BV-1 Inservice Test Program Proposed Revision 11 PUMP RELIEF REQUEST 6 A review of past test results has shown that this combination of quarterly and refueling frequency testing is capable of assessing pump performance and detecting degradation.
The use of the portable ultrasonic flow meter and full-flow recirc flow path was considered for the quarterly test. It was determined, however, that use of the full-flow recirc line was impractical for quarterly testing. Testing quarterly using the temporary ultrasonic flow meter would lead to the increased probability of failure of the heat trace elements and to increased dose for the laborers who remove/re-install the insulation and the technicians who install the flow meters. In addition, additional calibrated flow instrumentation would have to be purchased to ensure the availability of the equipment. Permanently installing the flow meters would require a design change to the plant and the purchase of additional flow instrumentation. Performing the full-flow test quarterly and during cold shutdowns would not enhance our ability to assess the operability of the pumps enough to justify the increased cost or a system design change.
In addition, testing during refueling outages diverts manpower from other refueling tasks. These tests must be scheduled at a time in the outage when the Boric Acid Tanks are not required to be part of the Tech Spec boration flow path and must be coordinated with power supply outages. Even though the actual performance of the these tests may be completed in a relatively short time, the set-up and restoration time is approximately 8 - 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for each pump. Removing the tests from the outage schedule would allow a greater focus on other safety related tasks without impacting the level of quality and safety of the Boric Acid Transfer Pumps. In addition, a PRA risk evaluation has determined that there is no increase in risk for the performance of this test, whether on-line or during refueling outages. Therefore, it is requested to perform the full-flow test on a refueling frequency while on-line, typically in the weeks just prior to the refueling outage. Overall, proper monitoring of pump performance will be maintained via quarterly testing and full flow testing on a refueling frequency.
Alternate Test: In accordance with Position 9 of GL 89-04, test quarterly through a fixed resistance minimum flow recirculation line: assuming flow to be constant and measuring delta-P in 10ST-7.1(2), "Boric Acid Transfer Pump Operational Tests," and test at a refueling frequency while on-line in the weeks prior to a refueling outage or during refueling outages at "full-flow" through a larger recirculation line, using a portable ultrasonic flow meter in IOST-7.13(14),
Boric Acid Transfer Pump Full-flow Tests.
Separate vibration reference and acceptance criteria values will be used for the different test conditions of the recirc and full-flow tests.
References:
OM-6, Paragraph 5.2 and Table 2.
Generic Letter 89-04, Position 9.
NUREG- 1482, Paragraph 3.1.1.
BV-1 Inservice Test Program Proposed Revision 1I PUMP RELIEF REQUEST 6
Text
FENOC FENOCRoute Beaver Valley Power Station 168 SRPO. Box 4 FirstEnergyNuclearOperating Company Shippingport,PA 15077-0004 Mark B. Bezilla 724-682-5234 Site Vice President Fax: 724-643-8069 July 8, 2002 L-02-063 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Inservice Inspection Program, Proposed Revision 11 Attached for NRC review and approval is proposed Revision 11 to the Beaver Valley Power Station Unit 1 (BVPS-1) Inservice Testing (IST) Program. This revision incorporates a new relief request, Pump Relief Request No. 6 (PRR6), which is being submitted for NRC review and approval in accordance with 10 CFR 50.55a(a)(3)(i).
The BVPS-1 Boric Acid Transfer Pumps [lCH-P-2A and 2B] are currently tested on a quarterly frequency through a mini-flow recirculation line without measuring flow, and on a refueling frequency through a full-flow recirculation line while all required parameters are measured. This testing is in accordance with Position 9 of Generic Letter 89-04 and is documented in the current Pump Refueling Outage Justification No. 1 (PROJI).
PRR6 requests that as an alternative to the testing performed, the full-flow recirculation test be performed while on-line just prior to a refueling outage. Full-flow testing at this frequency will assist in our desire to minimize refueling outage durations and maximize work management, while not impacting the level of quality and safety of the Boric Acid Transfer Pumps.
Relief is needed because the ASME XI Code does not recognize testing on-line at any frequency other than quarterly. PRR6 provides the basis for why this alternative testing is acceptable. NRC approval of PRR6 is requested by February 8, 2003, in order to incorporate this planned testing prior to the BVPS-1 Fifteenth Refueling Outage currently scheduled to begin on March 8, 2003.
If you have any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Affairs/Corrective Action at 724-682-5284.
Sincerely, Mark B. Bezi
Beaver Valley Power Station, Unit No. 1 Inservice Inspection Program, Proposed Revision 11 L-02-063 Page 2 Enclosure c: Mr. D. S. Collins, NRR Project Manager Mr. D. M. Kern, NRC Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator
BEAVER VALLEY POWER STATION Unit 1 Inservice Testing (IST) Program For Pumps And Valves Proposed Revision 11 Preparer 5.7 ** q. Date:
IQR/OSC Meeting # Date:
Owner Approval Date: .
Approval Authority 0. Date:
BV-1 Inservice Test Program Proposed Revision 1I PUMP RELIEF REQUEST 6 Pump Asset No(s): 1CH-P-2A 1CH-P-2B System: 7 - Chemical and Volume Control Function: To supply borated water from the Boric Acid Tanks to the suction of the Charging HHSI pump for injection into the RCS for emergency boration.
Test Requirement: Per OM-6, Paragraph 5.2, "Test Procedure" and Table 2, "Inservice Test Parameters," flow rate shall be determined and recorded.
Basis for Relief: In accordance with 10CFR50.55a(a)(3)(i), relief is requested on the basis that the proposed alternatives would provide an acceptable level of quality and safety.
Testing the Boric Acid Transfer pumps using the emergency boration flow path is impractical during power operation because it would inject water with higher concentration of boric acid into the RCS which would result in a reactivity transient and subsequent reactor shutdown. Therefore, the code-required quarterly testing is performed using an alternate test loop as shown on the attached figure. During normal plant operations, the pumps are tested quarterly through [RO-1CH-ORBA-1 (2)], the restricting orifices in the minimum flow fixed resistance recirculation lines. However, there are no installed flow instruments in these recirculation lines. Because of the restricting orifices, the flow is assumed to be fixed and at its reference value. Delta-P and vibration are then measured and compared to the acceptance criteria. Position 9 of GL 89-04 states that "In cases where flow can only be established through a non instrumented minimum flow path during quarterly pump testing and a path exists at cold shutdowns or refueling outages to perform a test of the pump under full or substantial flow conditions, the staff has determined that the increased interval is an acceptable alternative to the Code requirements, provided that pump differential pressure, flow rate, and bearing vibration measurements are taken during this testing and that quarterly testing also measuring at least pump differential pressure and vibration is continued."
Therefore, in accordance with Position 9 of the GL 89-04, the pumps have also been tested through their full flow recirculation flow paths through [HCV 1CH- 110(105)], at a refueling frequency. For the full-flow recirc test, the flow is measured using a portable ultrasonic flow meter that has been "wet-flow" calibrated to within the +/-2% accuracy required by ASME. In order to install the flow meters, however, the insulation on the piping must be removed and the heat trace elements must be moved away from where the transducers and tracks will be installed. Moving the heat trace elements places stresses on them, which increases the probability of failure of the heat trace elements. The heat tracing on the boric acid piping is needed to support system operability.
Therefore, it is also impractical to test the pumps at a cold shutdown frequency.
BV-1 Inservice Test Program Proposed Revision 11 PUMP RELIEF REQUEST 6 A review of past test results has shown that this combination of quarterly and refueling frequency testing is capable of assessing pump performance and detecting degradation.
The use of the portable ultrasonic flow meter and full-flow recirc flow path was considered for the quarterly test. It was determined, however, that use of the full-flow recirc line was impractical for quarterly testing. Testing quarterly using the temporary ultrasonic flow meter would lead to the increased probability of failure of the heat trace elements and to increased dose for the laborers who remove/re-install the insulation and the technicians who install the flow meters. In addition, additional calibrated flow instrumentation would have to be purchased to ensure the availability of the equipment. Permanently installing the flow meters would require a design change to the plant and the purchase of additional flow instrumentation. Performing the full-flow test quarterly and during cold shutdowns would not enhance our ability to assess the operability of the pumps enough to justify the increased cost or a system design change.
In addition, testing during refueling outages diverts manpower from other refueling tasks. These tests must be scheduled at a time in the outage when the Boric Acid Tanks are not required to be part of the Tech Spec boration flow path and must be coordinated with power supply outages. Even though the actual performance of the these tests may be completed in a relatively short time, the set-up and restoration time is approximately 8 - 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for each pump. Removing the tests from the outage schedule would allow a greater focus on other safety related tasks without impacting the level of quality and safety of the Boric Acid Transfer Pumps. In addition, a PRA risk evaluation has determined that there is no increase in risk for the performance of this test, whether on-line or during refueling outages. Therefore, it is requested to perform the full-flow test on a refueling frequency while on-line, typically in the weeks just prior to the refueling outage. Overall, proper monitoring of pump performance will be maintained via quarterly testing and full flow testing on a refueling frequency.
Alternate Test: In accordance with Position 9 of GL 89-04, test quarterly through a fixed resistance minimum flow recirculation line: assuming flow to be constant and measuring delta-P in 10ST-7.1(2), "Boric Acid Transfer Pump Operational Tests," and test at a refueling frequency while on-line in the weeks prior to a refueling outage or during refueling outages at "full-flow" through a larger recirculation line, using a portable ultrasonic flow meter in IOST-7.13(14),
Boric Acid Transfer Pump Full-flow Tests.
Separate vibration reference and acceptance criteria values will be used for the different test conditions of the recirc and full-flow tests.
References:
OM-6, Paragraph 5.2 and Table 2.
Generic Letter 89-04, Position 9.
NUREG- 1482, Paragraph 3.1.1.
BV-1 Inservice Test Program Proposed Revision 1I PUMP RELIEF REQUEST 6