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MONTHYEARML20323A0182020-11-18018 November 2020 Corrected Final Scenarios 1 2 3. (Folder 3) ML20177A4932020-06-25025 June 2020 Enclosure a - Redacted Owners, Officers, Directors, and Executive Personnel Forms for Energy Harbor Corp., Energy Harbor Nuclear Corp., and Energy Harbor Nuclear Generation LLC L-20-191, Energy Harbor - Enclosed May 2020 NPDES Discharge Monitoring Report, Beaver Valley Power Station & Supplemental Monitoring Data for Outfall 001 (Dissolved Oxygen)2020-06-24024 June 2020 Energy Harbor - Enclosed May 2020 NPDES Discharge Monitoring Report, Beaver Valley Power Station & Supplemental Monitoring Data for Outfall 001 (Dissolved Oxygen) ML20140A3352020-04-22022 April 2020 Steam Generator Tube Inspection Discussion Points for April 22, 2020, Teleconference with Energy Harbor Nuclear Corp. and NRC ML20008D2232020-01-0808 January 2020 NRC Region I Twitter Feeds 10-1 to 12-31-2019 ML18058A9532018-02-27027 February 2018 Comments on BVPS SE ML18058A9852018-02-27027 February 2018 BVPS-1 License Condition Page L-16-092, Information Pertaining to Foreign Ownership, Control, or Influence. Part 4 of 62016-04-22022 April 2016 Information Pertaining to Foreign Ownership, Control, or Influence. Part 4 of 6 ML16132A3932016-04-22022 April 2016 Davis-Besse, and Perry - Information Pertaining to Foreign Ownership, Control, or Influence. Part 2 of 6 ML16132A3962016-04-22022 April 2016 Information Pertaining to Foreign Ownership, Control, or Influence. Part 5 of 6 ML16132A3942016-04-22022 April 2016 Davis-Besse, and Perry - Information Pertaining to Foreign Ownership, Control, or Influence. Part 3 of 6 ML16090A2312016-03-21021 March 2016 Aam Open House, Sign-in Sheets, March 21, 2016 ML15104A6922015-04-0909 April 2015 Aam Attendance List, April 9 2015 ML14098A2132014-04-0303 April 2014 Aam 2014, Sign-in Sheet ML13364A2832013-12-30030 December 2013 Announcement of 2014 Generic Fundamentals Examination Administration Dates-Letter Dated Dec 30, 2013 L-14-147, ODCM: Index, Matrix and History of ODCM Changes2013-03-20020 March 2013 ODCM: Index, Matrix and History of ODCM Changes ML12230A2312012-08-15015 August 2012 Attachment 2 - L-12-287, Response to NRC Request for Additional Information Regarding 10 CFR 50.46, 30-Day Report ML12164A7992012-06-11011 June 2012 Attachment 2 to L-12-184, Response to NRC Request for Additional Information Regarding 10 CFR 50.46, 30-Day Report (Non-proprietary Version) ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status L-05-080, Exhibit D (Part 4): Excerpt from the Beaver Valley and Perry 2005 License Transfer Application2011-06-13013 June 2011 Exhibit D (Part 4): Excerpt from the Beaver Valley and Perry 2005 License Transfer Application ML1112305642011-04-28028 April 2011 Aam Attendance List, April 28, 2011 ML1013303522010-05-13013 May 2010 Attendance Signing Sheet for Annual Assessment Meeting 5-4-2010 ML1009103152010-03-31031 March 2010 Sign-in Sheet for FENOC Meeting 3-31-10 ML0929305002009-10-24024 October 2009 Response to Citizen Power Issues ML0909202522009-03-31031 March 2009 Public Meeting Sign-in Sheet, 3/31/2009 L-09-028, Response to Request for Additional Information the 2008 Steam Generator Tube Inspection Report2009-02-20020 February 2009 Response to Request for Additional Information the 2008 Steam Generator Tube Inspection Report L-08-229, Responses to a Request for Additional Information in Support of License Amendment Request No. 07-0052008-08-0101 August 2008 Responses to a Request for Additional Information in Support of License Amendment Request No. 07-005 ML0808801572008-03-25025 March 2008 Beaver Valley Annual Assessment, Sign-in Sheets ML0804603992008-02-13013 February 2008 Power Reactor Inattentive Officer Findings 2004-Present ML0735202772007-12-17017 December 2007 Ohio Natural Heritage Data Request for Beaver Valley Power Station License Renewal ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0726705012007-09-18018 September 2007 EPU I&C Questions ML0726301142007-09-14014 September 2007 / P. Paquin Ltr Amendment to Certificate of Compliance No. 9208 for the Model No. 10-142B Package (TAC L24117)/S121170 ML0726303192007-09-14014 September 2007 P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List ML0712307312007-04-25025 April 2007 Attendance Roster from Annual Assessment Public Meeting ML0634705992006-12-14014 December 2006 Plant Service List ML0611603672006-04-25025 April 2006 Fenco Security Working Hours and Fatigue; Procedure No. NOP-LP-1005, Rev 0 ML0535402882005-12-16016 December 2005 Issuance of Conforming Amendments for Bv, Units 1 and 2; Perry, Unit 1 and Davis-Besse, Unit 1 Transfer of Ownership Interests to Fengenco - Amendment No. 13 to Indemnity Agreement B73 ML0611605532005-03-24024 March 2005 NRC Inspection Report 2005-004 Meeting Attendees ML0611604822005-03-22022 March 2005 NRC Inspection Report 2005-04 Meeting Attendees ML0611603792005-02-24024 February 2005 NRC Telecon Listing ML0404104922004-02-20020 February 2004 Order EA-03-009 Service List ML0505404642004-02-0909 February 2004 Dynamic Web Page Printout Dated 02/09/2004 Regarding Applied Violations for Nuclear Power Plants ML0325214292003-08-20020 August 2003 Westinghouse - Nuclear Safety Advisory Letter NSAL-03-6, High Net Heat Input, Dated 08/20/2003 ML0403406452003-06-19019 June 2003 Corrective Action of CR 02-00921, Design Engineering Will Coordinate a Review of Time Limits for Critical Actions with Operations Personnel and as a Part of the Site Latent Issue Review Program Validate Associated Fire Protection Time Criti ML0403406142003-05-23023 May 2003 Corrective Action of CR 02-00921, Due Date Extension ML0403406092003-05-22022 May 2003 Corrective Action of CR 02-00921, Due Date Extension ML0403406362003-05-14014 May 2003 Corrective Action of CR 02-00921, Due Date Extension ML0403406202003-05-14014 May 2003 Corrective Action of CR 02-00921, Due Date Extension ML0227704292002-09-26026 September 2002 Draft Response to 2nd RAI for Beaver Valley, Unit 2 Fresh Fuel Rack Study 2020-06-25
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I BV EPU I&C Questions (1) During the period of an inoperable LEFM, the plant Licensing Requirement Manual LR 3.8 (Leading Edge Flow Meter), action lb, requires performing the calorimetric heat balance measurement(calculation) using the feedwater flow venturis and RTD indications and maintain Thermal Power at _*98.6% of RTP steady state until the LEFM is restored to operable status.
An extended in-operability of the LEFM (beyond the time for the next required daily calorimetric heat balance calculation) and the consequential continued use of venturi for the feedwater flow measurement, raises concerns regarding the accuracy of the venturi measurements. The staff concerns are based on the following.
(A) The LEFMs in both units of the Beaver Valley Power Station (BVPS) are manufactured and installed by Caldon. In a July 8, 2004, ACRS meeting to consider the proposed generic communication on the use of ultrasonic flow measurement devices for measuring feedwater flow in nuclear plants, Caldon representative publically stated that there is a preponderance of data showing that in general nozzles(venturi) can only be counted on to measure accurately within an uncertainty of +/- 1.5% or so.
(B) Summary of September 17, 2004 staff and licensees meeting regarding use of
UFM devices for feedwater measurement states that BVPs, units 1 and 2 are essentially identical, but most of its life unit 2 has produced about 1.5% more power than unit 1. The licensee concluded that with both units measuring feedwater flow with venturi, unit 2 was at overpower by about 1.5%. Relying on the UFMs for feedwater flow measurement resulted in comparable power, production for both units and the unit 2 balance of plant indicators (notable plant conditions) were consistent with the expected design values.
The licensee representative (PKMJ Technical Services) further clarified these statements in a December 17,2004 Fax (from Ciocca to Ahmed) stating that the LEFM system installed on BVPS, unit 1 provided readings that were essentially the same as the unit 1 feedwater venturi meters. However, a pre-installation of LEFM system review for BVPS, unit 2 revealed that each of the listed five balance of plant indications, although not a very precise measurement of reactor power, fell between 1.1% and 1.7% beyond the predicted values. The venturis used for measuring feedwater flow were laboratory calibrated and reported the plant was at the licensed power level. After installation, the LEFM measurement identified that the venturi indications were low by 40 MW thermal, approximately 1.5% power. It is also stated that the calibration of a venturi provides the accuracy for a venturi D/P, which then must incorporate additional instrumentation uncertainties to obtain a mass feedwater flow whereas UFM provides an accuracy that can not be achieved with a venturi and the associated instrumentation.
(C) Calibrated venturi essentially has the same uncertainty as that of the laboratory calibration uncertainty of 0.25% Or better and repeatable. ASME standards PTC 6 and 19.1 explain the minimum uncertainty requirements and are followed by the industry to achieve the required flow measurement uncertainty of a calibrated instrument.
Staff Concerns (1) The first two underlined statements in section B above indicate that venturis in both units were laboratory calibrated and their measurement uncertainty should essentially be same as identified in section C. Licensee has not identified the cause of different measurement values as to why one unit venturi measured correct while the other did not. The five listed balance of plant indicators do not identify the cause of different measurement results.
(2) If Caldon statement in section A and PKMJ representative's last underlined statement in section B are credible to prove statements in section C wrong, then the licensee is requested to provide justifications for using venturi to measure flow with an acceptable accuracy at 98.6% of RTP. Our concern is that the reduced power is essentially the one that was to be measured by venturi if an LEFM was not installed to be credited for better accuracy. Venturis that met the standards and accuracy value mentioned in section C are used with an
expectation that their measurement uncertainty will remain within the 10CFR appendix K 2.0% uncertainty allowance and no overpower will be experienced.
With the uncertainty as stated by Caldon, the staff needs assurance that appendix K allowance will not exceed when venturi is measuring flow.