|
---|
Category:- No Document Type Applies
MONTHYEARML21168A1492021-06-0909 June 2021 Annual Meeting Attendees List ML20261H6032020-09-17017 September 2020 C-10's Certificate of Service for Motion for Leave, Reply to Oppositions and Exhibit INT053 ML20008D2232020-01-0808 January 2020 NRC Region I Twitter Feeds 10-1 to 12-31-2019 ML18136A8602018-05-16016 May 2018 02-2018 Aam NRC Staff List ML16349A1752016-12-21021 December 2016 MSFHI - Tables 1 and 2--Final 12-21-16 ML16203A4022016-06-15015 June 2016 06-15-16 - Publicly Available Documents Provided to Senator Markey in Response to His Letter Dated February 17, 2016, Pertaining to the Seabrook Station UFSAR Revisions 11, 12, 13, 14, and 15 ML16161A5872016-05-17017 May 2016 05-17-16, List of Publicly Available Documents Provided to Senator Edward Markey from Eugene Dacus, OCA Pertaining to the Seabrook Station UFSAR Revision 16 ML16146A1932016-04-28028 April 2016 License Renewal Application, April 28, 2016, Public Meeting - Meeting Attendance List ML16118A2112016-04-19019 April 2016 04-19-16 - List of Publicly Available Documents Provided to Senator Markey in Response to His Letter Dated February 17, 2016, Pertaining to the Seabrook Station UFSAR Chapter 3 ML16071A4422016-03-0606 March 2016 Receipt of External Hard Drive Containing Revised I/O Files from NextEra Seabrook Station Nuclear Power Plant Flood Hazard Re-evaulation Report (CAC MF36782) SBK-L-15120, Independent Spent Fuel Storage Installation (ISFSI) Ics/Eals2016-02-27027 February 2016 Independent Spent Fuel Storage Installation (ISFSI) Ics/Eals ML15072A0372015-03-0909 March 2015 Enclosures 1 and 2 - Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years and Affidavit ML14209A0262014-07-28028 July 2014 2014 Seabrook Annual Assessment Meeting Attendance List Sheet ML14182A3382014-06-30030 June 2014 FOIA/PA-2013-0332 - Resp 6 - Partial, Group H, Records Being Released in Their Entirety ML14182A1362014-06-30030 June 2014 FOIA/PA-2013-0332 - Resp 6 - Partial, Group I, Records Being Released in Part ML14182A1322014-06-30030 June 2014 FOIA/PA-2013-0332 - Resp 6 - Partial, Group G, Records Already Publicly Available ML14141A6272014-05-20020 May 2014 LTR-14-0288-Ticket - Senator Edward J. Markey Ltr. Information About NRC-Sanctioned Job Shadow Program with China ML14113A0582014-04-18018 April 2014 LTR-14-0224-Ticket - Senator Edward J. Markey and Senator Elizabeth Warren Ltr. Measures Needed to Protect Pilgrim Nuclear Power Station and the Seabrook Station Against Seismic Vulnerability ML15161A0402014-02-19019 February 2014 Draft Vital Inverter NOED 02191 SBK-L-14006, Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application Severe Accident Mitigation Alternatives Review. Part 3 of 32014-01-22022 January 2014 Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application Severe Accident Mitigation Alternatives Review. Part 3 of 3 ML14034A0212014-01-22022 January 2014 Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application Severe Accident Mitigation Alternatives Review. Part 2 of 3 ML14034A0202014-01-22022 January 2014 Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application Severe Accident Mitigation Alternatives Review. Part 1 of 3 ML15236A2732014-01-16016 January 2014 We the People, a National Whistleblower Organization ML14007A7152014-01-0707 January 2014 G20140030/LTR-14-0009-Ticket - Senator Jeanne Shaheen Email Seabrook - Piping/Plumbing (Constituent Correspondence) ML13364A2832013-12-30030 December 2013 Announcement of 2014 Generic Fundamentals Examination Administration Dates-Letter Dated Dec 30, 2013 ML13354B9542013-12-18018 December 2013 G20140055/LTR-13-0957-Ticket - Senator Edward Markey, Et Al., Ltr Requests the NRC Make No Decision on the 6/1/10, Request for the Seabrook Nuclear Power Plant for a 20 Year Operating License Until the Concrete Degradation Is Well Tested an ML13354C0052013-12-18018 December 2013 G20140010/LTR-13-0959-Ticket - Bert Knowles Ltr. Opposition for the Relicensing of the Seabrook Nuclear Plant ML12174A0332012-06-0404 June 2012 Region 1 Comments on Draft TIA for Seabrook ASR Issue ML12174A0462012-06-0404 June 2012 Preliminary Draft Response to Request for Technical Assistance for Seabrook Station Alkali-Silica Reaction Degradation of Concrete ML12131A3782012-05-10010 May 2012 Annual Assessment Meeting Signing Sheets April 2012 ML1211603332012-04-23023 April 2012 Detailed Questions for Seabrook ASR Public Meeting on April 23, 2012 ML12088A2142012-03-26026 March 2012 Concrete Degradation - Alkali Silica Reaction ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML12054A6432012-02-16016 February 2012 Nextera Control of Contractors for ASR Issues ML12088A2132011-07-20020 July 2011 Concrete Degradation - Alkali Silica Reaction ML1117218982011-06-21021 June 2011 Annual Assessment Meeting Attendance List, June 8, 2011 ML1104802952011-02-15015 February 2011 Attachment to E-mail, Willoughby to Miller, NRC Conference Call on Friday - Seabrook Annulus Debris Interceptor Approach Velocity ML1100504852011-01-0505 January 2011 Attachment to E-mail, Kilby, to Miller, Information Related to Seabrook'S Proposed H License Amendment Request ML1019304602010-03-25025 March 2010 List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants ML0927403272009-09-30030 September 2009 Seabrook Regulatory Conference Sign-in Sheets ML0913200902009-04-30030 April 2009 Annual Assessment Meeting Sign-in Sheet, 4/30/2009 ML0913305422008-11-0303 November 2008 Seabrook - Fire Protection of Safe Shutdown Capability (10CFR50, Appendix R, Revision 9 ML0810904032008-03-25025 March 2008 Annual Assessment Meeting Attendance List, 3/25/08 ML0808000362008-03-13013 March 2008 List of Attendees, 03/13/2008 Summary of Meeting with Eight Operating Nuclear Power Plant Licensees to Discuss Emerging Metallurgical Issues Certain Welds in Reactor Coolant System for Pressurized-Water Reactors ML0806704192008-03-0707 March 2008 CDBI Findings ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0731104102007-10-17017 October 2007 Enclosure 2 to Fple Letter SBK-L-06227 - Emergency Initiating Condition Matrix, Modes 1, 2, 3, & 4 ML0731104072007-10-17017 October 2007 Enclosure 1 to Fple Letter SBK-L-06227 - Summary Explanation Providing the Necessary Justification for Changing the Basis of the Fple Seabrook Emergency Action Level (EAL) Scheme from NUREG-0654 to NEI 99-01, Revision 4 ML0731104132006-12-29029 December 2006 Enclosure 4 to Fple Letter SBK-L-06227 - Seabrook Emergency Classification System, Section 1-5.1 Through 1.5.11 ML0634705992006-12-14014 December 2006 Plant Service List 2021-06-09
[Table view] |
Text
REVIEW SCOPE SPWB has been assigned responsibility for review of the thermal-hydraulic aspects of UFM applications. All other aspect$ that contribute to uncertainty, such as transducer characteristics, physical dimensions, signal processing, operations other than those that may affect velocity profile, operator-display interfaces, and long-term degradation, are not part of this assigned responsibility. This safety evaluation is limited to the thermal-hydraulic aspects of the Check and CheckPlus UFMs and consideration of uncertainty is limited to those aspects directly associated with SPWB's assigned responsibility. This safety evaluation addresses, for example, assessment of the hydraulic aspects of laboratory test facilities, actual UFM testing, fidelity of the test configuration to the plant installation insofar as potential effect on velocity profile is concerned, in-situ (in-plant) calibration, operational considerations that may change the velocity profile, and use oftother independent plant instrumentation to assess the UFM output and hence provide a Ipotential means for identifying a change in velocity profile.
This review has two objectives within the above-described technical scope:
- 1. Assess the Seabrook request for a measurement uncertainty recapture (MUR) uprate
- 2. Provide a generic assessment of the Caldon Check and CheckPlus UFMs.
There is significant duplication in applicable references. During the review, we initially worked with slides provided in meetin gs with the NRC since the slides provided the best summaries of the material under review and these descriptions were often adequate to cover the review scope. We used other references as appropriate to incorporate more detail.
TABLE OF CONTENTS
- 1. INTRODUCTION AND CONCLUSIONS
- 2. BACKGROUND
- 3. REVIEW OF THE CHECK AND CHECKPLUS ULTRASONIC FLOW METER 3.1 Check and CheckPlus Characteristics 3.2 Calibration Considerations 3.3 Pre-delivery - Calibration 3.4 Commissioning 3.5 Operation t 3.6 Other Considera:ions
- 4. REFERENCES
- 1. INTRODUCTION AND CONCLUSIONS By a letter dated September 22, 2005, FPL Energy Seabrook, LLC requested an amendment to its facility operating license and the plant technical specifications for Seabrook Station (Reference 1). The license amendment request was for a measurement uncertainty recapture (MUR) power uprate to increase the licensed reactor core thermal power level by 1.7 percent from 3587 MW to 3648 MW. In its letter, Seabrook stated that the license amendment request was developed consistent with the Nuclear Regulatory Commission (NRC) guidelines provided in Reference 2. Seabrook further stated that the LEFM design was addressed in Topical Reports ER-80P and ER-157P (References 3 and 4) that were approved by the NRC staff. By memos dated January 24, 2006 and February 1, 2006 (References 5 and 6, respectively), the NRC staff identified additiona: information to support its review. In response to these communications, supplemental information was provided in Reference 7. Additional information was obtained in meetings with Seabrook and Caldon at NRC (References 8 and 9), from a meeting with Seabrook and Caldon at the Alden Research Laboratories (ARL)
(Reference 10), and in additional information submitted in Reference 11.
The NRC staff evaluated the theoretical bases for the CheckPlus, pre-delivery testing at ARL, and the hydraulic aspects associated with the plans for installation and certification at Seabrook and for long-term operation. The NRC staff also audited the hydraulic aspects of the Check and CheckPlus UFMs that have been installed in 44 nuclear power plant feedwater pipes to obtain additional insight into expected behavior when the CheckPlus is installed and operated in the Seabrook plant. With respect to the Seabrook request, the NRC staff finds:
- The CheckPlus hydraulic characteristics as described in the above licensee references are accurately portrayed.
The hydraulic aspects, of the CheckPlus and the claimed associated uncertainties are acceptable for the determination of feedwater flow rate at the Seabrook nuclear power plant in support of the 'requested measurement uncertainty recapture uprate.
Therefore, the NRC staff findsl that the requested measurement uncertainty recapture uprate amendment is acceptable. However, during implementation, the licensee shall complete the activities associated with installation, certification, and long term operation consistent with the descriptions of such activities provided to the NRC and consistent with the information provided in the remainder of this safety evaluation.
A fundamental aspect of the Seabrook review was to address generic issues discussed in Reference 12. The NRC staff has completed a generic re-examination of the hydraulic aspects of Check and CheckPlus operation to address these issues. The NRC staff finds that the hydraulic aspects of Check and CheckPlus systems have been accurately described in applicable Caldon documentation, that there is a firm theoretical and operational understanding of behavior, and, with one exception, there is no further need to re-examine the hydraulic bases for use of the' Check and CheckPlus systems in nuclear power plant feedwater applications. The exception, Which is considered to be a confirmatory item with respect to the Seabrook review, is to establiqh the effect of transducer replacement on the Check and CheckPlus system uncertainties.