Letter Sequence RAI |
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MONTHYEARML14246A4552014-09-0808 September 2014 Acceptance Review of License Amendment Request Measurement Uncertainty Recapture Power Uprate Project stage: Acceptance Review ML14303A2792014-11-0404 November 2014 Request for Additional Information Regarding License Amendment Request to Support a Measurement Uncertainty Recapture Power Uprate for Catawba Unit 1 Project stage: RAI 2014-11-04
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Category:Letter
MONTHYEARML24255A8312024-09-23023 September 2024 Project Manager Assignment ML24261B9782024-09-19019 September 2024 Notification of an NRC Fire Protection Team Inspection NRC Inspection Report 05000413-2024010, 05000414-2024010 and Request for Information IR 05000413/20243012024-09-16016 September 2024 Operator Licensing Examination Approval 05000413/2024301 and 05000414/2024301 IR 05000414/20240912024-09-0505 September 2024 Final Significance Determination of a White Finding and Nov and Assessment Followup Letter-NRC Inspection Report 05000414-2024091 IR 05000413/20240052024-08-26026 August 2024 Updated Inspection Plan for Catawba Nuclear Station (Report 05000413/2024005 & 05000414/2024005) ML24235A1542024-08-22022 August 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000413-2024402 and 05000414-2024402) IR 05000413/20240022024-08-0808 August 2024 Integrated Inspection Report 05000413-2024002 and 05000414-2024002 and Apparent Violation IR 05000413/20244032024-08-0101 August 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000413/2024403; 05000414/2024403 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24178A0552024-06-26026 June 2024 Requalification Program Inspection – Catawba Nuclear Station IR 05000414/20240902024-06-24024 June 2024 NRC Inspection Report 05000414/2024090 and Preliminary White Finding and Apparent Violation ML24170A8632024-06-11011 June 2024 Flowserve June 11, 2024, Part 21 Notification - Redacted Version for Publishing ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) ML24144A1162024-05-28028 May 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000413/20240012024-05-10010 May 2024 Integrated Inspection Report 05000413/2024001 and 05000414/2024001 and Apparent Violation ML24095A1072024-04-0808 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report (C1R27) ML24017A0652024-03-0808 March 2024 Issuance of Amendment Nos. 319 and 315 to Technical Specification 3.7.11, Control Room Area Chill Water System (Cracws) IR 05000413/20230062024-02-28028 February 2024 Annual Assessment Letter for Catawba Nuclear Station Units 1 and 2 - (NRC Inspection Report 05000413/2023006 and 05000414/2023006) IR 05000413/20230042024-02-0202 February 2024 – Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue 2024-09-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24197A1702024-07-15015 July 2024 Request for Additional Information Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations ML24150A1662024-05-29029 May 2024 Document Request for Catawba Nuclear Station Units 1 & 2 - Radiation Protection Inspection - Inspection Report 2024-03 ML23271A1792023-09-28028 September 2023 Request for Confirmation License Amendment Application to Revise Control Room Cooling TS 3.7.11 ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML22336A0692022-11-28028 November 2022 Final 2023 Catawba Nuclear Station (CNS) Commercial Grade Dedication (CGD) Inspection Information Request ML22154A1312022-06-0303 June 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Environmentally-Assisted Fatigue License Renewal Commitment ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22102A2962022-04-13013 April 2022 Request for Withholding Information from Public Disclosure Response to Request for Additional Information ML22063B1782022-03-0909 March 2022 Request for Additional Information Regarding LAR for Revision to the Conditional Exemption of the End of Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) NON-PROPRIETARY ML22024A1122022-01-24024 January 2022 2022 CNS POV Inspection Information Request ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21335A2252021-12-0101 December 2021 NRR E-mail Capture - Catawba Nuclear Station, Unit 2 - Request for Additional Information Spring 2021 Steam Generator Tube Inspection Report (L-2021-LRO-0043) ML21117A1232021-04-23023 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request Request for Additional Information ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20346A0212020-12-10010 December 2020 NRR E-mail Capture - Formal Release of RAIs - License Amendment to Change TS 3.8.1 Due Jan. 29, 2021 ML20338A3932020-12-0303 December 2020 Notification of Inspection and Request for Information ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20244A0462020-08-31031 August 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20073F3832020-03-13013 March 2020 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station - SG Report (RA-19-0391) - C2R23 ML20050D3382020-02-21021 February 2020 Letter RAI 1 MAGNASTOR-Catawba and McGuire Exemptions with Enclosure ML20052E4282020-02-21021 February 2020 Notification of NRC Fire Protection Team Inspection (Fpti) (NRC Inspection Report 05000412/2020013 and 05000414/2020013) and Request for Information ML20003E5372020-01-0303 January 2020 NRR E-mail Capture - Catawba PT Limits LAR - RAIs ML19032A5842019-01-31031 January 2019 Emergency Preparedness Program Inspection Request for Information ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19009A5412019-01-0909 January 2019 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Esps LAR ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18068A5052018-03-0909 March 2018 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Nsws Return Pond Header LAR (CACs MG0245 and MG0246, EPID L-2017-LLA-0297) ML18058B2062018-02-27027 February 2018 Notification of Inspection and Request for Information ML18057A2182018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to A. Zaremba Request for Additional Information for Review of Duke Energy'S Decommissioning Funding Plan Update) ML17335A0972017-11-29029 November 2017 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Relief Request 17-CN-001 (CACs MF9807 and MF9808, EPID L-2017-LLR-0032) ML17135A0302017-05-12012 May 2017 NRR E-mail Capture - Request for Additional Information - Catawba TSTF-197 ML17115A1422017-04-25025 April 2017 NRR E-mail Capture - Request for Additional Information - Catawba SG Report - RFO 21 ML16337A3322017-01-12012 January 2017 Request for Additional Information Regarding License Amendment Request for Electrical Power System Alignments for Shared Systems ML16355A3922016-12-29029 December 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program ML16292A2252016-10-14014 October 2016 Emergency Preparedness Inspection and Request for Information ML16271A0752016-10-12012 October 2016 Request for Additional Information Regarding License Amendment Request for Electrical Power System Alignments for Shared Systems ML16222A7472016-08-0909 August 2016 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML16205A0022016-07-21021 July 2016 Notification of Inspection and Request for Information ML16187A0662016-07-0707 July 2016 Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program (CAC Nos. MF2936 and MF2937) ML16111B2472016-04-28028 April 2016 Request for Additional Information Re. License Amendment Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML16120A0872016-04-27027 April 2016 Notification of Inspection and Request for Information ML16113A0732016-04-22022 April 2016 Draft RAIs License Amendment Request to Revise TS Section 5.5.2 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16007A1902016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Change the RCS Minimum Required Flow Rates ML16014A7102016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme ML15348A2602015-12-17017 December 2015 Request for Additional Information Regarding License Amendment Request to Use an Alternative Fission Gas Gap Release Fraction ML15320A3862015-11-19019 November 2015 RAI LAR to Adopt TSTF-523 ML15314A3562015-11-10010 November 2015 E-mail from J. Whited to A. Zaremba Duke Energy Draft RAIs License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15314A3592015-11-10010 November 2015 Duke Energy Draft RAIs Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) 2024-07-15
[Table view] |
Text
UNITED STATES*
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 4, 2014 Mr. Kelvin Henderson Site Vice President Catawba Nuclear Station* .
Duke Energy Carolinas, LLC 4800 Concord Road York, NC 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2: REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO SUPPORT A MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE FOR CATAWBA, UNIT 1 (TAC NOS. MF4526 AND MF4527)
Dear Mr. Henderson,
By letter dated June 23, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14176A109), Duke Energy Carolinas, LLC submitted a license amendment request to increase the Catawba, Unit 1, authorized core power level from 3,411
- megawatts thermal (MWt) to 3,469 MWt, an increase of approximately 1. 7 percent rated thermal power.
The U.S. Nuclear Regulatory Commission (~RC) staff has reviewed the licensee's submittal and determined that additional information is needed in order to complete the NRC staff's review. Enclosure 1 describes this request for additional information (RAI). Responses to the RAis are requested within 45 days.
If you have any questions, please call me at 301-415-2481.
Sincerely, J .
I C: ,J}1 '" '1 Q . r d Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO SUPPORT THE MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE DUKE ENERGY CAROLINAS, LLC
- CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 TAC NOS. MF4328 AND MF4329 By letter dated June 23, 2014, Duke Energy Carolinas, LLC, the licensee for Catawba Nuclear Station, Units 1 and 2 (Catawba), requested a measurement uncertainty recapture (MUR) power uprate (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14176A109). The proposed revision would increase the Catawba, Unit 1, authorized core power level from 3411 megawatts thermal (MWt) to 3469 MWt, ah increase of 1. 7 percent rated thermal power (RTP). *
- Based on the review of the amendment request, the NRC staff has determined that additional information is required regarding the MUR power uprate Division of Safety Systems, Reactor Systems Branch (SRXB) - RAI 1
\
Cameron Measurement Systems, ML205, Revision 0, "Methodology for Calculating the Weighted Average of Several Measurements, Each Having an Estimated Uncertainty, to Minimize the Uncertainty of the Results," (ADAMS Accession No. Ml12075A212) provides guidance for assessing long-term operational feedwater flow rate calibration of chordal leading edge flow meters (LEFMs) by comparison to other plant parameters. The Cameron methodology takes the estimated uncertainty of each plant parameter into consideration and states that; "If an unaccounted bias in the LEFM is to be detected by best estimate trending, it is desirable to start the trend at the commissioning of the LEFM." Ple*ase discuss how ML205 will be implemented as part of procedures associated with the MUR uprate.
SRXB-RAI2 Caldon Customer Information Bulletin, CIB119, Revision 0, "Checklist Confirm-ing theLEFM~
and LEFM~+ Systems are Operating Within Design Basis," (ADAMS Accession No. ML12075A211) provides for on-line monitoring of the inputs to the CheckPILis feedwater flow .
computation. In Table 3, Field Verification of Input Uncertainties, under Category Dimensions, an unstated assumption appears to be made that corrosion products are never removed in the short-term during operation. Please confirm that CIB119, Revision 0, will be followed while addressing the identified observation. ;*
Enclosure
SRXB- RAI3 Section Ill of the application contains the accidents and transients for the existing analyses of record that do not bound plant operation at the proposed uprated power level. The loss-of-coolant accidents (LOCAs) are reviewed for the impact of the MUR power uprate under this section. The licensee states the following that, "Based on power levels assumed in current best-estimate large-break LOCA analyses (1 01 percent of 3411 MWt plus 1 percent uncertainty), it has been determined that the peak clad temperature (PCT) analysis is not bounded by the uprate. However, there is a PCT analysis performed at a best-estimate power of 101.7 percent of 3411 MWt with 0.3 percent uncertainty that will be included in the updated final safety analysis report (UFSAR) once the NRC approves the MUR LAR [license amendment resquest]." Please clarify if the methodology used for the PCT analysis for the MUR., that would be included in the UFSAR, is the same as the current unbounded PCT analysis.
SRXB- RAI4 The best-estimate power levels used in the new PCT analysis are 101.7 percent of 3411 MWt with 0.3 percent uncertainty compared to the unbounded analysis power levels of 101 percent of 3411 MWt plus 1 percent uncertainty. Please provide a justification for why these best-estimate power levels of 101.7 percent of 3411 MWt with 0.3 percent uncertainty is appropriate for the new PCT analysis compared to 101 percent MWt of 3411 MWt plus 1 percent uncertainty.
SRXB- RAI5 Please provide the PCT analysis performed,at a best-estimate power of 101.7 percent of 3411 MWt with 0.3 percent uncertainty to confirm the accident and transient bounding for plant operation at the proposed Llprated power level.
SRXB- RAI6 Please provide WCAP-1680316083 1-NP, Revision 1, "Benchmark Testing of the FERRET Code for Least Squares Evaluation of Light Water Reactor Dosimetry," April 2013.
SRXB- RAI7 The NRC staff is not aware of any benchmarking that qualifies RAPTOR-M3G for Catawba.
Please provide plant-specific benchmar~ing for Catawba.
1 During the RAI clarification call on October 22, 2014, the licensee stated that the correct document number for the Topical Report referenced is WCAP-16083-NP, Revisioi11. The NRC staff had incorrectly identified it as WCAP-16803-NP, Revision 1..
Division of Safety Systems, Containment and Ventilation Branch (SCVB) RAI 1 Please verify that the control area ventilation system, the auxiliary building ventilation system and the diesel building ventilation system remain bounded for the design basis (1 02 percent of 3411 MWt) for the MUR power uprate conditions. 2 Division of Risk Assessment, Fire Protection Branch (AFPB) RAI 1 , "Summary of RIS [
Regulatory Issue Summary] 2002-03 Requested Information," to LAR, Section 46, "Safe Shutdown Fire," states that, " ... The CNS Fire Protection System is utilized for certain non-fire
- protection purposes. During a B.S.b event, all AC power is lost and portable pumps are used to charge the underground fire protection system header. Catawba uses the underground fire protection system header to distribute water to meet B.S.b strategies inCluding makeup to the spent fuel pool, the refueling water storage tank, and steam generators as well as fire suppression and Containment flooding. Operations emergency procedures for loss of feedwater provide an option to use water from the fire protection system header to make up to the steam generators ... "
It is unclear to the NRC staff whether other uses of fire water for non-fire protection purposes at Catawba, Units 1 and 2, will impact the need to meet the fire protection system design demands. The NRC staff requests the licensee to discuss any changes to non-fire suppression use of fire protection water as a result of the MUR and how this change will impact the need to meet the fire protection system design demands or confirm that these uses remain unchanged as a result of the MUR.
Division of Engineering, Mechanical and Civil Engineering Branch (EMCB) RAI 1 The primary system critical parameters listed in Table IV-1 (Page E2-44) of CATAWBA LAR are not consistent with the parameters listed in the FSAR [final safety analysis report], Revision 15 as shown below:
Table IV-1 of LAR Table 5-1 of FSAR Revision 15 Reactor flow (E+06 lbm/hr) 147.8 145.3 T hot (°F) 614.4 613.9 T cold. (°F) 555.8 556.3 Steam temperature (°F) 548.73 547 Steam pressure (psia) 1021 1020 Please clarify the differences.
2 During the RAI clarification call on October 22, 2014, the licensee stated that the information being sought in SCVB RAI 1 could be found on page E2-83 of the licensee's June 23, 2014 submittal. The
- NRC staff agreed that the information is contained in the submittal and that this RAI is no longer necessary.
Division of Engineering, Steam Generator and Chemical Engineering Branch (ESGB)
RAI1 Confirm that the steam generator plugging limit is still appropriate for the proposed MUR Power Uprate conditions, given the guidance in Regulatory Guide 1.121.
ESGB RAI2 Page E2-67 of Enclosure 2 of the LAR provides the predicted wear rates for run definition
'HS4/D-1 51 Stg Drain' with component name 1HS817E-T196. The information in the table for this component indicates that the post-MUR predicted thickness value is -0.048 inches. Further, the ratio of pre-MUR measured thickness to predicted thickness is -5.13. Please clarify what these values represent and the significance of them being negative numbers.
ML14303A279 *Via E-mail OFFICE NRR/LPLI-1/PM NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/88/SCVB NRR/88/SRXB SFigueroa RDennig NAME AChereskin GEM iller (SRohrer for) (JRaval for)* US hoop DATE 10/23/14 11/03/14 11/03/14 10/10/14 10/09/14 OFFICE NRR/DE/EMCB* NRR/DE/ESGB NRR/DRNAFPB* NRR/LPL2-1/BC NAME Tlupold GKulesa AKiein RPascarelli DATE 10/07/14 11/03/14 09/18/14 11/04/14