Text

Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
	ML19066A088
Person / Time
Site:	Grand Gulf
Issue date:	03/06/2019
From:	Emily Larson; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	GNRO-2019/00012, TSTF-425
	Download: ML19066A088 (136)
	v • d • e

-\*.

~Entergx Entergy Operations, Inc.

P.O. Box756 Port Gibson, Mississippi 39150 Eric A. Larson Site Vice President.

Grand Gulf Nuclear Station Tel 601-437-7500 10 CFR 50:90 GNR0-2019/00012 March 06, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justificati9n for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)

Grand Gulf Nuclear Station, Unit 1 NRC Docket No*. 50-416 Renewed Facility Operating License No. NPF-29 By letter dated April 12, 2018 (Reference 1), as supplemented by letter dated June 7, 2018 (Reference 2), Entergy Operations, Inc. (Entergy) requested a license amendment to modify the Grand Gulf Nuclear Station, Unit 1 (GGNS) Technical Specifications by relocating specific surveillance frequencies to a licensee-controlled program with the implementation of Nuclear Energy Institute 04-10, "Risk-Informed Technical Specification Initiative Sb, Risk-Informed Method for Control of Surveillance Frequencies."

By email correspondence dated October 31, 2018, (Reference 3), the U.S. Nuclear Regulatory Commission (NRC) provided three requests for additional information (RAls) in support of the license amendment request. By letter dated November 30, 2018 (Reference 4), Entergy responded to the RAls. In this response, Entergy also indicated that a supplemental response would be provided to RAI No. 1 during the first quarter of 2019. The supplemental response would provide the results of an internal events (IE) .sensitivity study of GGNS plant failure data, since August 2012, to determine if a further update to the GGNS IE Probabilistic Risk Assessment (PRA) model would be warranted.

The Enclosure to this letter provides the IE PRA sensitivity study performed on GGNS plant failure data for the six year period from September 2012 to August 2018. The information provided herein does not change the intent or the justification for the requested license amendment and does not alter the conclusion that the proposed license amendment does not involve a significant hazards consideration..

GNR0-2019/00012 Page 2 of 3 No new regulatory commitments are made in this submittal.

In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," a copy of this application,' with attachments, is being provided to designated State of Mississippi Official.

If you should have any questions regarding this submittal, please contact Douglas A. Neve, Manager, Regulatory Assurance, at (601) 437-2103.

I declare under penalty of perjury that the foregoing is true and correct. Executed on oath day of March 2019.

Respectfully, Eric A. Larson EAL/rws

Enclosure:

Grand Gulf Nuclear Station Probabilistic Risk Assessment Data Sensitivity Study, Report No. ENTGGGX083-RPT-001

References:

1) Letter from E.A. Larson (Entergy) to NRC, "Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)," dated April 12, 2018 (NRC Agencywide Documents Access and Management System (ADAMS)

. Accession No. ML181028445)

2) Letter from E.A. Larson to NRC, "Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specitic Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)," dated June 7, 2018

. (ADAMS Accession No. ML18158A514) )

3) Electronic mail from L. M. Regner (NRC) to D. A. Neve and J. Schrage (Entergy),

Subject:

"Final Request for Additional Information -TSTF.-425 (L-2018-LLA-0106)," October 31 2018, 3:10 PM

4) Letter from E.A. Larson to NRC, "Response to Request for Additional Information for Technical Specification Change* Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program* (TSTF-425)," dated November 30, 2018 (ADAMS Accession No. ML18337A136)

GNR0-2019/00012 Page 3 of 3 cc: NRG Region IV, Regional Administrator NRG Senior Resident Inspector, Grand Gulf Nuclear Station NRG Project Manager, Grand Gulf Nuclear Station State Health Officer, Mississippi Department of Health

I~

Enclosure GNR0-2019/00012 Grand Gulf Nuclear Station Probabilistic Risk Assessment Data Sensitivity Study Report No. ENTGGGX083-RPT-001 .

132 Pages

ENERCON PROJECT REPORT COVER SHEET face!!ence-Every project Every day.

Title:

Grand Gulf Nuclear Station REPORT NO.: ENTGGGX083-RPT-001 Probabilistic Risk Assessment Data Sensitivity Study REVISION: 0 Client: Entergy, GGNS Project Identifier: ENTGGGX083 Item Cover Sheet Items Yes No 1 Does this Project Report contain any open *assumptions, including preliminary information that require confirmation? (If YES, identify the D [g]

assumptions.)

2 Does this Project Report supersede an existing Project Report? (If YES, identify the superseded Project Report.)

- D ~

Superseded Project Report No.

Scope of Revision:

Initial Issue.

Revision Impact on Results:

Initial Issue.

Safety-Related 1 D Non-Safety-Related C8J (Enter Name and Sign)

Digit.lily signed by Gregory P Rozga Originator: Gregory P. Rozga DN: cn=Gregory P Rozga, o=Enercon, ou=PRA.

~rt. email=grozga@e11ercon.com, c=US Date: 2019.01.11 16,06:46 *-06"00' Design Verifier 1 (Reviewer for Non-Safety-Related}: Robert Lichtenstein !. /-r: /*** gg~7:fifif:~~~~~ ~u D1!ijt~!ly ~ig:Md by Stn'en ~hlilii'J.,.

Steve Phillippi D~: i.:n=S.k"IE-n ?N!lii=it<i, o:.:ENE!KCN ~ivic,~s, :n,.

-ff.:~--- :;:.:~~tt*<:::::- (m::eM.}rne.QrP?.AS.:rv:U~

t>1,,.ail"'H>hi!t1ppk~n~n:c11tr.cim. r....ll:i Dat<r.2019.01.1117:l&*U*CS'OO' Digirally signed by Diane M. Jones Approver: Diane Jones ,,..r~)r"; ON: cn=Oiane M. Jones, o=Enercon ~rvices, Inc., ou=PRA, email=djones:~~nercon.com, Date: January 2019 c=IJS Date: 2019.01.1411:05:35 *06'00' Note 1: Design Verification is required for all safety-related Project Reports. A review 1s adequate for non-safety-related Project Reports.

ENTGGGX083-RPT-001 Data Sens.itivity Study Page 2 of 132 Table of Contents 1.0 Scope ........................................................................................................................................ 3 2.0 Time Period of Sensitivity Analysis .......................................................................................... 3 3.0 Initiating 'Events Sensitivity Analysis ........................................................................................ 4 4.0 Unavailability Data Sensitivity Analysis .................................................................................... 5 5.0 Reliability Data Sensitivity Analysis .......................................................................................... 7 6.0 Quantification .......................................................................................................................... 9 7.0 Results and Conclusions ......................................................................................................... 10 8.0 References ...........................................................................................................................,.. 11 Appendix A - GGN.S lnjtiating Event LER Data ........................................................................... 12 Appendix B - Bayesian Update Worksheet for Initiating Events ................,............................... 26 Appendix C - Unavailability Calculation ...........................,. ........................................................ 30 Appendix D - Flag File UA.txt ...................................................... ~ .............................................. 89 Appendix E - CR Functional Failure Review ...............................,. ............................................... 94 Appendix F - GGNS Functional Failures ................................................................................... 111 Appendix G - Runtime and Demand Estimates ....................................................................... 115 Appendix H - GGNS_R4B-Rel-Sens.rr Bayesian Data ............................................................... 118 Appendix I - Data Source History and File Lists from Prior Models of Record ........................ 123

\

ENTGGGX083-RPT-001 Data Sensitivity Study Page 3 of 132 1.0 Scope A sensitivity study was performed on the GGNS Rev. 48 internal events PRA by updating the initiating events (IE), unavailability and reliability data. In the Rev. 48 PRA model, the data analysis had a cutoff date of 8/2012 and was last updated as part of the Rev. 4A model revision. This sensitivity study updated the data to include initiating events, unavailability time and function failures over the six year period of 9/2012 - 8/2018 for risk significant components. The potential impact on common cause failure probabilities was not addressed as part of this sertsitivity analysis, nor was the impact of more recent generic data sources.

Note that the risk significance of a component was generally not a condition when performing this analysis. The IE update included the incorporation of all initiating events experienced at GGNS during the period of this analysis. The test and maintenance unavailability update included updating all unavailability events in the model to include data during the period of this analysis. Finally, with respect to reliability data, only equipment which experienced at least one functional failure during the analysis period were evaluated. Equipment which did not have a functional failure was conservatively not evaluated, since an increase _in the number of demands or runtime without any additional functional failures would tend to decrease the failure rate.

2.0 Time Period of Sensitivity Analysis The number of reactor critical hours for GGNS 9/2012 to 8/2018 was downloaded from the NRC website (https://www.nrc.gov/reading-rm/doc-collections/event-s tatus/reactor-status/). These 41,688 hours0.00796 days 0.191 hours 0.00114 weeks 2.61784e-4 months were appended to the prior 46,930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months from the Rev. 4A Data Analysis [Table 8 of Ref. 1] for a total of 88,618 reactor critical hours over the time period for this analysis from 9/2006 to 8/2018.

2012 2013 2014 2015 2016 2017 2018 January 336 744 744 744 72 552 February 672 216 504 456 672 624 March 744 312 744 96 744 744 April 720 720 720 720 480 144 May 744 744 744 744 744 0 Ju nae 720 720 720 552 720 0 July 720 744 744 312 744 480 August 696 744 744 744 696 744 September 720 720 720 720 192 0 October 744 600 744 744 0 744 November 720 648 720 720 0 384 December 552 744 744 744 0 576 TOTAL 2736 8064 7872 8592 4560 6576 3288 Note: Any power level for a given day assumed to be 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at that power level Total online time 09/12 - 08/18 41688 hrs Total operating years 4.76 yrs

ENTGGGX083-RPT-001 Data Sensitivity Study Page 4 of 132 Note that the total calendar time used in, the Rev. 4A Data Analysis was 52,608 hours0.00704 days 0.169 hours 0.00101 weeks 2.31344e-4 months [Table 8 of Ref. l].

-The calendar time from 9/2012 to 8/2018 is 52,584 (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months less thanthe prior 6 year period due to leap year). The total calendar time from 9/2006 to 8/2018 is 105,192 hours0.00222 days 0.0533 hours 3.174603e-4 weeks 7.3056e-5 months .

3.0. Initiating Events Sensitivity Analysis Initiating events occurring at GGNS from 9/1/12 - 8/31/18 were identified and incorporated into the PRA. The analysis wa.s performed by reviewing the latest initiating events summary on the NRC website (initiating-event-summary-2016.xlsx ori webpa*ge https://nrcoe.inl.gov/resultsdb/lnitEvent/) which fncluded data up to December 2016; however, the most recent initiating event for GGNS included in the NRC summary was 6/25/2016. A total of ten (10) GGNS initiating events occurred during this data period. For the time period from 6/25/2016 - 8/31/2018, an LER search on the NRC website identified another four (4) GGNS initiating events.

Of the fourteen (14) initiating events identified for GGNS during the period of 9/1/12 - 8/31/18, one (1) was classified as QR4 - Core Power Excursion (RPS Trip), eight (8) were classified as QR5 -Turbine Trip, and the remaining five (5) were classified as QR6 - Manual Reactor Trip. Upon review of the LER abstracts, it was determined that one (1) event can be categorized as a %T2 (Loss of PCS) initiator, twelve (12) events can be categorized as a %T3A (PCS Available Transient) initiator, and one (1) event can be categorized as a %T3B (Loss of Condensate Feedwater Pump Transient) initiator. The LERs are contained in Appendix A.

This new initiating event data was used to revise the Rev. 4A Bayesian update spreadsheets for %T2 (FRCalc99-T2M-rxyrs--Split.xls), %T3A (FRCalc99-T3A-rxyrs.xls) and %T3B (FRCalc99-T3B-rxyrs.xls). The previous analysis for %T2 had seven (7) events over 23.31 reactor years from July 1, 1986 to August *31, 2012. This sensitivity study added one {1} new %T2 event over 4.76 reactor years from September 1, 2012 to August 31, 2018. This results in eight (8) failures over 28.07 reactor years from July 1, 1986 to August 31, 2018. The resulting file is named FRCalc99-T2-rxyrs-Sens.xls (Appendix B). The result of this analysis is no change to the %T2 IEF as it remained 1.12E-01/rcy.

The previous analysis for %T3A had five (5) %T3A events over 5.61 reactor years from May 22, 2006 to August 31, 2012. This sensitivity study added twelve (12) new %T3A events over 4.76 reactor years from September 1, 2012 to August 31, 2018. This results in seventeen (17) failures over 10.37 reactor years from May 22, 2006 to August 31, 2018. The resulting file is named FRCalc99-T3A-rxyrs-Sens.xls (Appendix B). The result of this analysis increased the %T3A IEF from 8.31E-01/rcy to 8.53E-01/rcy for about a 2.6% increase.

The previous analysis for %T3B had ten (10} events over 23.31 reactor years from July 1, 1986 to August 31, 2012. This sensitivity study added one (1) new %T3B event over 4.76 reactor years from September 1, 2012 to August 31, 2018. This results in eleven (11) failures over 28.07 reactor years from July 1, 1986 to August 31, 2018. The resulting file is named FRCalc99-T3B-rxyrs-Sens.xls (Appendix B). The result of this analysis is a slight decrease in the %T3B IEF from 2.38E-01/rcy to 2.37E-01/rcy.

To incorporate this information during quantification, a flag file was created to update the IEFs prior to quantification. The flag file is named, IE.txt, and contains a single line for each initiator:

%T2 PROB 1.12E-01

%T3A PROB 8.53E-01

ENTGGGX083-RPT'-001 Data Sensitivity Study Page 5 of 132

%T3B PROB 2.37E-01 These lines set the IEFs of events %T2, %T3A and %T3B to their updated values prior to quantification.

The value of %T2 did not change as part of this data update; however, the initiating event is included in the flag file to demonstrate that it was evaluated.

Note that there were no other initiating event types which occurred at GGNS during the time period of this sensitivity analysis. Updating t~ese other initiating events would result in lowering all other IEFs as the number of reactor critical years would be increased by 4.76 rcy in all other calculations with no corresponding increase in the number of events. However, no other initiating events were updated for this sensitivity analysis. This will result in a conservative bias when quantifying the impact of this sensitivity analysis.

4.0 Unavailability Data Sensitivity Analysis The probability of all test and maintenance unavailability events in the Rev. 48 internal events PRA was updated by gathering out of service (DOS) data over the time period of this sensitivity study, adding it to the Rev. 4A unavailability data, and extending the exposure time to include the time of this sensitivity study. This analysis is documented in Excel file "GGNS Unavailability - Sensitivity Update.xlsx11 [Ref. 2].

Upon review of the GGNS data, there were several issues identified which required the application of assumptions. These issues included: 1) the use of calendar time vs. reactor critical time for most of the unavailability events, 2) the use of non-provided reports to calculate 005 time outside of the Data Ana!ysis notebook [Ref. 1], and 3) undocumented reasoning for non-zero unavailabilities calculated in the Data Analysis notebook [Ref. 1] which are set to zero (0) in the PRA model.

With respect to issue 1}, note that Section 5.5 of the Data Analysis notebook [Ref. 1] states, "The plant exposure for maintenance events is calculated from the generator available hours for each unit at GGNS.

Only reactor critical hours are considered relevant for maintenance calculations, meaning that any testing or maintenance which occurs during shutdown periods is not part of the exposure time."

Nevertheless, in 106 of the 162 unavailability basic events evaluated, the calendar time of 52,608 hours0.00704 days 0.169 hours 0.00101 weeks 2.31344e-4 months (from September 1, 2006 -August 31, 2012}, or 26,280 hours0.00324 days 0.0778 hours 4.62963e-4 weeks 1.0654e-4 months (used for the two unavailability basic events for new air compressors added around September 2009) was used as the exposure time. There was no basis identified for the use of calendar time. Only 54 of the unavailability events used the reactor critical hours of 46930. (Note that two other events used some other time due to extenuating circumstances which were justified.)

It is not the intention of this sensitivity analysis to review the Rev. 4A analysis, or to determine the bases for prior decisions. Rather, this analysis will update the data previously developed using the same methodology as was used in the Rev. 4A analysis. Therefore, to maintain consistency with the current calculation of test and maintenance unavailabilities, in cases where calendar hours were used in the Rev. 4A analysis, calendar hours for the new data period were added to determine the revised exposure hours. In cases where reactor critical hours were used, reactor critical hours for the new data period were added to determine the revised exposure hours. (An MCR should be written to investigate the inconsistency in the u~availability exposure periods.)

Regarding item 2), in cases where an outside report was used to estimate the unavailability (e.g., see event L20-BAT-MA-1H1 in Appendix C where the entry in the "Original Rev. 4A Notes" says "MCR GG-

ENTGGGX083-RPT-001 Data Sensitivity Study Page 6 of 132 4962") the OOS time was back-calculated (i.e., unavailability x exposure hours = 005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ). For this analysis, it is assumed that the unavailability has not changed. For completeness, an updated OOS time*

was calculated based on the assumed unavailability and the updated exposure time. Note that this does not mean that this OOS is accurate, it merely provides an estimated OOS time which can be reviewed by plant personal to ensure the OOS time is reasonable. Cases like this are annotated so it is clear that the unavailability is not documented in this analysis.

Regarding item 3), the following 36 unavailability events were found in the Rev. 48 model (CAFTA Reliability Database Editor file GGNS_R4B.rr) to be set to zero (0) even though a non-zero unavailability was calculated in the Data Analysis Notebook [Ref. 1]:

L20-BAT-MA-1H1 LSl-BCC-MA-lGS L62-INV-MA-1Y99 N19-HTX-MA-B003C L20-BAT-MA-1H2 L51-BCC-MA-1K4 N19-HTX-MA-BOOlA N19-HTX-MA-B004A L20-BAT-MA-1J 1 LSl-BCC-MA-lKS N~9-HTX-MA-B001B N19-HTX-MA-B004B L20-BAT-MA-1J2 LS l-BCC-MA-1 L4 N19-HTX-MA-B001C N19-HTX-MA-B004C '

LSO-BCC-MA-1H4 LSl-BCC-MA-lLS N19-HTX-MA-B002A P47-MDP-MA-C001C LSO-BCC-MA-lHS L51-BCC-MA-2G4 N19-HTX-MA-B002B P4 7-M DP-MA-COOlF LSO-BCC-MA-1J4 L51-BCC-MA-2GS N19-HTX-MA-B002C P4 7-M DP-MA-COOlL LSO-BCC-MA-lJS L62-INV-MA-1Y80 N19-HTX-MA-B003A PSl-DRY-MA-DRYA L51-BCC-MA-1G4 L62-INV-MA-1Y82 N19-HTX-MA-B003B PSl-DRY-MA-DRYB Since no documentation could be found as to why these 36 non-zero unavailabilities were set to zero in the PRA model, all unavailabilities calculated in this sensitivity analysis were used in the quantification.

Note that some unavailabilities were calculated to be zero, these are set to zero. A (non-documented) test case, in which these 36 events were reset to zero, demonstrated that there was no discernable impact in CDF or LERF. Neither the CDF nor the LERF values changed; the only impact was on the number of LERF cutsets which slightly decreased. This demonstrates that these specific unavailability 1

events are not significant events.

The update of the test and maintenance unavaifabilities are documented in Appendix C. The Appendix C data includes the test and maintenance unavailability basic event from the PRA, along with a description of the event, the OOS and exposure hours for each basic event, and the unavailability. In addition, a column marked "Original Rev. 4A Notes" contains the unaltered notes from the Rev. 4A analysis. The information in this column usually contains the document number of a calculation, or details of assumptions made to estimate the OOS time, exposure time or both. The final column (Sensitivity Case Notes) cqntains any notes added as part of this sensitivity update. If a "Sheet" is listed (e.g., Sheet "P75 Hours), it identifies the worksheet The 005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months come from either Maintenance Rule (MR) spreadsheets [Ref. 3] which collect OOS hours for select systems, or scaled up estimates from the Rev. 4A data. Note that it is not clear if the MR spreadsheets only collect the 005 time during reactor critical hours; however, to be consistent with the Rev. 4A [Ref. 1] analyses, it is assumed that the hours only represent OOS hours when the reactor is critical. Note that this assumption is conservative since including 005 time when the reactor is not critical results in higher unavailabilities.

Thi;! exposure hours are estimated as described above. There are only 4 unique exposure times used in the analysis.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 7 of 132

105,192 hours0.00222 days 0.0533 hours 3.174603e-4 weeks 7.3056e-5 months is the calendar time during the data collection period (9/1/06 - 8/31/18); this is used for 104 unavailability basic events when calendar time was used in the Rev. 4A analysis.

88,618 hours0.00715 days 0.172 hours 0.00102 weeks 2.35149e-4 months is the reactor critical time during the data collection period; this was used for 54 unavailability basic events when reactor critical time was used in the Rev. 4A analysis.

78,888 hours0.0103 days 0.247 hours 0.00147 weeks 3.37884e-4 months (used for two unavailability basic events) is an estimate of the exposure time for the Train A and B P51 (Plant Air) system compressors which, based on the MR data sheets, was brought*

online around September 2009. The Rev. 4A analysis used 26,280 calendar hours. There are approximately 78,888 calendar hours from September 2009 through August 2018.

54, 792 hours0.00917 days 0.22 hours 0.00131 weeks 3.01356e-4 months (used for two unavailability basic events) is an estimate of the exposure time for the L and M P47.(Radial Well) pumps which was brought on line June 1, 2012 [Ref. 1, Note 1 of Table 13].

The Rev. 4A analysis used one calendar year (8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months ). There are approximately 54792 calendar hours from June 1, 2012 through August 2018.

The flag file UA.txt (see Appendix D) was created to use during quantification. This flag file will set the test and maintenance unavailability basic events to their new values calculated in Appendix C prior to quantification.

5.0 Reliability Data Sensitivity Analysis A reliability sensitivity analysis was performed for all equipment (equipment types) which experienced a functional failure during the period of this sensitivity study. Note that this is conservative since equipment which did not experience any functional failures sho_uld see at least a slight increase in their reliability sinJ:e their exposure time or number of demands have increased without experiencing any additional failures.

The reliability analysis was performed by reviewing condition reports accompanying functional failures.

Each condition report is reviewed to determine if the failure could impact (either explicitly or implicitly) a PRA component. If it can be determined that the functional failure would not impact a PRA component, then it can be documented as such and disregarded. However, if the functional failure impacts a PRA component, then that failure is used to update the type code failure rate for the component type. For example, if condition report describes the failure of a PRA MOV to open, then the type code for MOV fail to open (i.e., MOV CC) is adjusted for the failure using Bayesian Updating.

A total of 169 condition reports (CRs) containing MR functional failures (MRFF) was provided by GGNS.

These CRs were reviewed and 54 PRA functional failures were identified. Note that the majority of MRFFs were related to systems or components not modeled in the PRA. It should also be noted that when identifying if a functional failure would impact a PRA component, this review not only looked at the basic events from the PRA model, it also reviewed the EOOS mapping table to ensure that functional failures on equipment which are implicitly modeled (i.e., equipment mapped to a PRA component) are captured. A functional failure is only determined to have no impact on reliability if it is not explicitly modeled in the PRA, and if it is not mapped to any PRA component in EOOS. Appendix E documents this MRFF review.

As with the initiating events and unavailability analyses, the reliability analysis will span the time period from 9/1/0~ - 8/31/18. For PRA functional failures, this is accomplished by appending the results of the Appendix E review to the table of PRA functional failures from Rev. 4A [Table 6 of Ref. 1]. The combined results are presented in Appendix F. The Appendix F data can be distilled to determine the number of

ENTGGGX083-RPT-001 Data Sensitivity Study Page 8 of 132 PRA functional failures for each type code; this is shown below. As previously stated, for this sensitivity analysis, only those type codes with functional failures will be updated; all other component failure modes will not be adjusted. Hence, only the type codes shown below will be updated.

Type Code # FF Type Code # FF Type Code # FF Type Code # FF AOVCC 1 CBROO 1 MCS FS 1 MOVCC 1 AOVOC 3 CKVOO 3 MDC FR 12 MOVOC 4 ASLDN 2 DGN Fl 4 MDCFS 2 MOVOO 2 ASP DN 1 DGN FS 2 MDP FR 3 PTR LP 1 BAT LP 1 EPVCC 1 MDS FR 1 TDP FR 1 CBRCC 2 FNS. FR 2 MDS FS 2 TDS FS 2 CBRCO 1 FNS FS 1 MOD CC 7 TIM DD 2 In order to perform the Bayesian Update, the number of exposure (i.e., runtime) hours, or demands

{whichever is applicable for the failure mode in question) during the data period must be determined.

The exposure hours or demands are estimated in one of two ways based on the way it was done in the previous Rev. 4A analysis [Ref. 1]. In the first way, plant data was collected for major equipment and entered into a spreadsheet called App c-1.xlsx [Reference 24 of Ref. 1]. When the exposure hours or demands were collected in this fashion, the data in App c-1.xlsx is_ updated assuming the number of hours or demands during the old data period (9/2006 - 8/2012) is the same as the new data period (9/2012 - 8/2018) since the calendar time is the same (6 years). This is an assumption which may be non-conservative since the capacity factor decreased between the two time periods, but it is considered reasonably accurate for ttiTs sensitivity analysis.

The second method of determining the exposure hours or number of demands (when plant data is not easily available) is based on hours of critical operation (for runtime), or the testing frequency of the system {for demands). For runtime failures, such as spurious operation of valves, the total exposure hours for the failure mode of interest are calculated as the number of reactor critical hours in the period of interest (which for this analysis is 88,618 hours0.00715 days 0.172 hours 0.00102 weeks 2.35149e-4 months ) times the number of components in the PRA with that failure mode. For example, if there are 10 valves with a spurious open failure mode modeled in the PRA, then the exposure time for the spurious open failure mode is 886,180 hours0.00208 days 0.05 hours 2.97619e-4 weeks 6.849e-5 months . For demand-based failure, an assumption is made where each component receives one demand per test. Therefore, if there are 20 valves which are tested quarterly (every 3 months), and 10 that are tested during each refueling cycle (assume every 24 months), the number of demands can be calculated as 20 * (# of critical months/3) + 10 * (# of critical months/24). Given the number of critical months over the 12 calendar years of this analysis is 121.39, the above equation results in 859 demands of these 30 valves over the analysis period.

This information is contained in spreadsheet "Comp Dem and Exp - Sens.xlsx [Ref. 4]. Note that this 1

spreadsheet was adapted from spreadsheet "GGNS Plant Component Demands and Exposures.xlsx '

[Reference 23 of Ref. 1], and therefore, there are numerous worksheets which are not used. Only the worksheets pertaining to type codes which need to be updated are edited. In addition, there were type

ENTGGGX083-RPT-001 Data Sensitivity Study Page 9 of 132 codes which were not included in either App c-1.xlsx, or GGNS Plant Component Demands and*

Exposures.xlsx; hence, new worksheets were added for those type codes.

Appendix G contains the results of the exposure hour and demand estimates. The last column identified whether the first method (update the App c-1.xlsx data}, or the second method (updating the Comp Dem and Exp - Sens.xlsx data} was used.

The number of functional failures and either exposure hours or demands calculated above were entered into the CAFTA Reliability Database Editor using the Bayesian Updating module. The CAFTA file used from the Rev. 48 PRA was GGNS_R48.rr, and the file with the updated information is now named GGNS_R4B-Rel-Sens.rr (see Quantification Section below for file details}. In all cases, the prior information came from the 2010 update of NUREG/CR-6928 [Ref. 5] which is the data source used in the Rev. 46 PRA for all other reliability data. The Bayesian Update information from the CAFTA Reliability database is presented in Appendix H.

6.0 Quantification The quantification was performed by quantifying the Rev. 46 PRA model using the revised reliability database file, and applying the two flag files developed in the Initiating Events {IE.txt} and Unavailability (UA.txt} sections above. Quantification was performed using PRAQuant {Ver. 5.la} with the FTREX (Ver.

1.8.0.1) engine.

Prior to quantification of this sensitivity analysis, a confirmatory quantification was performed to ensure that the GGNS Rev. 48 cutsets could be reproduced using the code versions on the author's computer.

The results for both CDF and LERF were exact, and delete term operations were performed in both directions to ensure that the cutsets in both the Rev. 46 model, and the author's quantification were exact.

The input and output files from the sensitivity analysis are (see Appendix I for this information from prior models of record):

File CDF LERF GGNS_R4B-new IF.caf Fault Tree 12/23/2018 1:13 PM 784 KB GGNS_R4B-Rel-Sens.rr Database 12/30/2018 12 :08 AM 6000 KB CDF-Both.qnt LERF-STG.qnt PRAQuant File 1/4/2019 4:33 PM 1/4/2019 5:01 PM 3 KB 3 KB GGNS Rev 48 CDF w LOOP.txt GGNS Rev 48 LERF w LOOP.txt Master Recovery 12/23/2018 1:13 PM 12/23/2018 1:22 PM File 191 KB 108 KB FLG_GGNS_R4B-NOFLEX.txt Master Flag File 12/23/201$ 1:25 PM 1 KB

ENTGGGX083-RPT-001 Data Sensitivity Study Page 10 of 132 File CDF I LERF I IE.txt Initiating Event 1/4/2019 4:03 PM Sequence Flag File 1 KB UA.txt Unavailability 12/30/2018 9:28 PM Sequence Flag File 7 KB

CDF.CUT #LERF.CUT Cutset File 1/4/2019 4:30 PM 1/4/2019 4:47 PM 12,578 KB 21,910 KB I

The results of the quantification are provided below:

Case Results Increase % Increase Base CDF 2.58E-06 Sensitivity CDF

2.96E-06 3.80E-07 14.7%

Base LERF 7.74E-07, Sensitivity LERF 9.38E-07 1.64E-07 21.2%

7.0 Results and Conclusions This data sensitivity analysis was performed for the GGNS Rev. 48 PRA by extending the data sampling period to include more recent plant data spanning from 9/2012 - 8/2018 (see Appendix I for the data sources from prior models of record). The sensitivity analysis updated the initiating event frequencies (IEFs), test and maintenance unavailabilities and' reliabilities used in the GGNS Rev. 48 PRA.

The initiating event update reviewed all GGNS initiators, and resulted in changes to only two (2) initiating events (%T3A and %T3B) being updated. There was an additional %T2 initiating event, but the Bayesian Update resulted in no change to the IEF. There were no other initiators that occurred during this time period. Not updating the IE frequency for those initiating events with no additional occurrences is conservative since incorporating additional exposure time without any new events will tend to lower the IEF.

Like the initiators, the r~liability updates were limited to those component failure modes which experienced a functional failure during this time period. Not updating the other failure modes is conservative since incorporating additional exposure time or demands without any.new functional failures will tend to lower the failure frequency.

The unavailability analysis included all unavailability events modeled in the PRA. One potent,ial issue identified during this analysis was that most of the exposure time for the unavailability events uses calendar time vs. reactor critical time. This is non-conservative since the use of calendar time increases the denominator in the calculation resulting in a smaller unavailability. Note that the impact of this non-conservatism is offset by the conservatism in the initiating event and reliability analyses.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 11 of 132 The results of the analysis show an approximate CDF and LERF increase of 15% and 21%, respectively.

Note that even with these increases, the overall CDF and LERF are still small.

8.0 References

1) PSA-GGNS-01-DA, "Grand Gulf Nuclear Station Plant Specific Data and CCF Notebook, Rev. Oa.

2) GGNS Unavailability - Sensitivity Update.xis; 12/30/2018 8:59 PM; 733 KB.

3) MR 005 Data Sheets:

a. 821.xls, 12/28/2018 1:46 PM, 891 KB.

b. CH.xis, 12/28/2018 1:46 PM, 473 KB.

c. C41.xls, 12/28/2018 1:46 PM, 698 KB.

d. C71.xls, 12/28/2018 1:46 PM, 919 KB.

e. E12.xls, 12/28/2018 1:46 PM, 691 KB.

f. E21.xls, 12/28/2018 1:46 PM, 291 KB.

I

g. E22.xls, 12/28/2018 1:46 PM, 258 KB.

h. E30.xls, 12/28/2018 1:46 PM, 488 KB.

i. E51.xls, 12/28/2018 1:46 PM, 286 KB.

j. P41.xls, 12/28/2018 1:47 PM, 677 KB.

k. P41.xls, 12/28/2018 1:47 PM, 677 KB.

I. P51 Rev 1.xls, 12/28/2018 1:47 PM, 1,010 KB.

m. P53.xls, 12/28/2018 1:47 PM, 373 KB.

n. P64.xls, 12/28/2018 1:47 PM, 677 KB.

o. P75_81.xls, 12/28/2018 1:47 PM, 970 KB.

p. T48.xls, 12/28/2018 1:47 PM, 462 KB.

q. TSl.xls, 12/28/2018 1:47 PM, 1,175 KB.

r. X77.xls, 12/28/20181:47 PM, 664 KB.

s. Y47.xls, 12/28/2018 1:47 PM, 4,149 KB.

4) ((Comp Dem and Exp - Sens.xlsx" 12/29/2018 11:58 PM, 64 KB

5) "Component Reliability Data Sheets Update 2010", United States Nuclear Regulatory Commission (USNRC), NUREG/CR-6928 Supplement, September 2012.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 12 of 132 Appendix A - GGNS Initiating Event LER Data (September 1, 2012 -August 31, 2018)

ENTGGGX083-RPT-001 Data Sensitivity Study Page 13 of 132 NRC Code Mapped LER Number Event Date Abstract Code Description GGNS IE 4162012008 12/29/2012 QRS Turbine On December 29, 2012, at 00:18 Central Standard Time, Grand Gulf Nuclear %T3A Trip Station was operating in Mode 1 at 100 percent thermal power when an unexpected Reactor SCRAM occurred due to a Main Generator trip. All systems responded as expected with the exception of Safety Relief Valve (SRV) 1B21F047A, which was slow to close, and high pressure feedwater heater start-up outlet valve 1N21F010B, which did not open. The shift immediately

/

entered the appropriate Off Normal Event Procedures. Reactor water level was controlled using the normal condensate/feedwater system throughout the event. All control rods inserted after Reactor Protection System signals were received. There were no Emergency Core Cooling System actuations. The plant was stabilized with pressure control on the main turbine bypassNalves, and level controlled on the start-up level control valve. The plant responded to the trip as designed with the exception of the one SRV and one start-up outlet valve noted above. The cause of the SCRAM was not initially determined.

Additional monitoring equipment was installed to detect a similar condition.

Following a second SCRAM on January 4, 2013, the cause was determined to be grounding of the Main Generator 'A' Phase Neutral Current Transformer.

There were no adverse effects on the health and safety of the public.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 14 of 132 NRC Code Mapped LER Number Evenn:>ate Abstract Code Description GGNS IE 4162013001 1/4/2013 QRS Turbine At 23:37 Central Standard Time on January 4, 2013, Grand Gulf Nuclear Station %T3A Trip experienced an unexpected Reactor SCRAM caused by a Main Generator trip.

The plant was operating in Mode 1 at 94 percent thermal power. All safety systems responded per design. Safety Relief Valves opened at the onset of the event to control reactor pressure and reseated properly. All control rods inserted when the signals generated by the Reactor Protection System were received. There were no Emergency Core Cooling System actuations. The shift immediately entered the appropriate Off Normal Event Procedures. The plant was stabilized with pressure control on the main turbine bypass valves and level control on the start-up level control valve, although high pressure feedwater heater start-up outlet valve 1N21F010B did not open. The cause of the SCRAM was the Main Generator 1A 1 Phase Neutral Current Transformer (CT) experienced partial grounding due to inadequate clearance between the micarta plate bolts and bottom of the CT allowing the conductors to come in contact with a bolt providing a shunt path to ground. This was caused by inadequate workmanship and work instructions not specifying the clearance during installation. There were no adverse effects on the health or safety of the public as a result of this event. The micarta plate bolts were subsequently removed or cut to provide adequate clearance prior to plant restart.

ENTG GGX083-RPT-001 Data Sensitivity Study Page 15 of 132 NRC Code Mapped LER Number Event Date Abstract Code Description GGNS IE 4162013002 1/14/2013 QR5 Turbine At 18:05 Central Standard Time on Januariy 14, 2013, Grand Gulf Nuclear %T3A Trip Station experienced an automatic Reactor SCRAM caused by a Turbine Trip due to a Main Generator-lockout. The plant was operating in Mode 1 at 100 percent thermal power. All safety systems responded per design. Safety Relief Valves opened at the onset of the event to control reactor pressure and reseated properly. All control rods inserted when the signals generated by the Reactor Protection System were received. There were no Emergency Core Cooling System actuations. The shift immediately entered the appropriate

- procedures. The plant was stabilized with pressure control on the main turbine bypass valves and level control on the start-up level control valve, although high pressure feedwater heater start-up outlet valve 1N21F010B did l

not open when placing the start-up level control valve in service. There were no adverse effects on the health and safety of the public as a result of this event. The cause of the SCRAM was the Main Generator Isolated Phase Bus Cooling System experienced partial grounding due to design configuration of the horizontal bushing in an energized section of the bus, in close proximity to a degraded viewing port, which allowed water accumulation that created a ground condition. Additional portions of the isophase bus with seal off bushings were de-energized, and covers were installed over the viewing ports prior to plant restart.

ENTG GGX083-RPT-001 Data Sensitivity Study Page 16 of 132 NRC Code Mapped LER Number Event Date Abstract Code Description GGNS IE 4162013003 7/30/2013 QRS Turbine At 14:32 Central Daylight Time on July 30, 2013, Grand Gulf Nuclear Station %T3A Trip experienced an unexpected Reactor SCRAM from 100% thermal power due to

high reactor pressure detected by the Reactor Protection System. Operations staff immediately entered the appropriate off-normal event procedures.

Reactor Core Isolation Cooling (RCIC) initiated and injected briefly during the transient, The RCIC initiation signal was valid, but not required to maintain the reactor vessel water level. Reactor levels were verified and RCIC was subsequently secured. All other systems operated as expected. Reactor pressure was controlled by discharging steam to the main condenser via the main turbine bypass valves. Reactor water level was controlled using the condensate and feedwater systems via the startup level control valve. No safety relief valves actuated. The cause of the SCRAM was a human performance-induced error due to inadequate troubleshooting activities on the Turbine Stress Evaluator (TSE). A temperature transmitter failure was not recognized nor corrected, thereby resulting in a high turbine stress temperature signal. Upon restoration of the TSE, the incorrect signal forced turbine control valves in the closed direction and resulted in a high reactor pressure transient. Procedures and work orders are being revised to prevent recurrence of this event. There were no adverse effects to the health and safety of the public.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 17 of 132

- Mapped NRC Code LER Number Event Date Abstract Code Description GGNS IE 4162014002 3/17/2014 QR6 Manual On March 1?, 2014, at 05:14 Central Daylight Time with the plant at 41 %T2 Reactor percent rated core thermal power during power ascension from refueling Trip outage 19, Grand Gulf Nuclear Station manually actuated the Reactor Protection System (RPS} to shut down the reactor due to a steam leak in the turbine building. All control rods fully inserted and all safety systems operated as designed. The Main Steam Isolation Valves (MSIVs) were manually shut and the Reactor Core Isolation Cooling (RCIC) System was manually initiated. No Safety Relief Valves (SRVs) actuated automatically. Manual cycling of SRVs and RCIC was used to maintain reactor water level and pressure within normal bands. Group 2 and 3 Residual Heat Removal (RHR) isolation signals were received. However, no valve movement occurred since the affected valves are normally closed. The cause of the manual RPS actuation was a steam leak in the turbine building resulting from a failed turbine first stage pressure sensing line (TFSPSL) followed by a failed main steam line four inch drain line. The failed drain line has been replaced and both TFSPSLs have been removed.

Temporary modifications have been issued for implementation of "a current source" strategy. This action removes the TFSPSLs and installs two electronic modules as an interim action while a design change to eliminate the need for the TFSPSLs is being developed. The event posed no threat to public health and safety.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 18 of 132 NRC Code Mapped LER Number Event Date Abstract Code Description GGNS IE 4162014003 3/29/2014 QRS Turbine On March 29, 2014, at 10:08 Central Daylight Time with the plant at 87 %T3A Trip percent rated core thermal power, Grand Gulf Nuclear Station experienced an automatic actuation of the reactor protection system and plant scram due to a Main Turbine Overspeed Protection Load Reject Relay (LRR) fault. All control rods fully inserted and safety systems operated as designed. No safety relief valves lifted and no isolation signals were received. Reactor Water Level increased, resulting in a Level 9 SCRAM signal which caused an automatic trip of both reactor feed pumps to reduce reactor water inventory. However,_

reactor feedwater was promptly restored. The cause of the event was an L-RR fault which caused a fast closure signal to the Main Turbine Control Valves (TCV). The TCV closure resulted in the automatic actuation of the reactor protection system and plant scram. Investigations determined the cause of !he LRR fault was a failed ceramic capacitor on a Multiplier Module (MM) card.

-* The failed MM card has been replaced as well as the LRR power supply, power measurement input module and voltage measurement input module. The event posed no threat to public health and safety. '

ENTG GGX083-RPT-001 Data Sensitivity Study Page 19 of 132 NRC Code Mapped LER Number Event Date Abstract Code Description GGNS IE 4162015001 2/7/2015 QR5 Turbine On Saturday, February 7, 2015, at 1856 hours0.0215 days 0.516 hours 0.00307 weeks 7.06208e-4 months Central Standard Time, with the %T3A Trip plant at 100 percent thermal power, Grand Gulf Nuclear Station experienced an automatic actuation of the reactor protection system (RPS) and subsequent 11 11 reactor SCRAM. The 8 main transformer differential trip caused a generator lockout. The generator lockout was followed by a turbine control valve fast closure (RPS SCRAM signal), turbine trip and reactor SCRAM. All control rods fully inserted and safety systems operated as designed. Eleven safety relief valves (SRVs) lifted to control pressure. Feedwater was manually secured to transfer to the startup level control mode. There were no emergency core cooling systems (ECCS) actuations required or initiated in response to this SCRAM. Turbine bypass valves opened to stabilize pressure causing reactor water level to fluctuate. Residual heat removal (RHR) group 2 and 3 containment isolation signals were received on low level 3. A hard ground was discovered on the non-safety protective circuitry between the current 11 11 transformer and control cabinet on 8 main transformer. The faulted cables and other similar cables were determinated and alternate wiring and conduit was installed before placing the transformers back into s~rvice. The event posed no threat to public health and safety.

J

ENTGGGX083-RPT-001 Data Sensitivity Study Page 20 of 132 NRC Code Mapped LER Number Event Date Abstract GGNS IE Code Description 3/29/2016 QRS Turbine On March 29, 2016, at 1123 Central Daylight Time, Grand Gulf Nuclear Station %T3A 4162016002 Trip was operating in Mode 1 and ascending in power at approximately 37% when an unplanned uncomplicated automatic reactor SCRAM occurred. A generator 1 1 lockout was received due to a Main Transformer 8 Differential Relay Trip which was followed by a turbine control valve fast closure, turbine trip, and reactor SCRAM. The Reactor Protection System and all other safety systems 1 1 functioned as designed. The cause of the Main Transformer 8 Differential 1 1 Relay Trip was identified during forced outage investigation of the 8 Main Transformer control cabinet. The high voltage current transformer wiring was incorrectly landed ~t the Xl/X2 terminals instead of the X1/X3 terminals. This wiring configuration resulted in a turns ratio of 1000:5 instead of the designed 2200:5, causing relay actuation at a point lower than designed. The erroneous 1 1 wiring configuration was corrected and all remaining wiring for the 'A', 8 , and

'C' Main Transformer wiring was verified correct prior to startup from the forced outage. This event posed no threat to public health and safety.

6/17/2016 QR4 Core On June 17, 2016, at 0256 Central Daylight Time, Grand Gulf Nuclear Station %T3A 4162016004 Power experienced an automatic reactor scram. Prior to the scram, Grand Gulf Excursion Nuclear Station was operating in Mode 1 at approximately 65% rated thermal (RPS Trip) power and performing the Turbine Stop and Control Valve Operability Surveillance. During the surveillance, after the 8 Turbine Stop valve was 1 1 closed per procedure, the 'D' Turbine Stop Valve unexpectedly closed. The 'A' and 'C' Turbine Control Valves were then challenged to control Turbine and Reactor pressure resulting in Reactor pressure and power oscillations. The causes of this event were inadequate procedural guidance and the failure to use conservative decision making strategy. Corrective actions included replacement of the defective solenoid valves, and the revision of the applicable testing and Operations performance standards procedures.

ENTG GGX083-RPT-001 Data Sensitivity Study Page 21 of 132 NRC Code Mapped LER Number Event Date Abstract Code Description GGNS IE 4162016005 6/25/2016 QR5 Turbine On June 25, 2016, at 1407 Central Daylight Time, Grand Gulf Nuclear Station %T3A Trip was operating in Mode 1 at approximately 98.75 percent rated thermal power, performing final power ascension to 100% power with Reactor Recirculation Flow Control Valves, when an unplanned automatic reactor SCRAM occurred. All safety systems responded per design. Two Safety Relief Valves opened at the onset of the event to control reactor pressure and reseated properly. All control rods inserted when the signals generated by the Reactor Protection System were received. There were no Emergency Core Cooling System actuations. The shift immediately entered the appropriate Off Normal Event Procedures. The plant was stabilized with pressure control on the main turbine bypass valves and level control on the start-up level co'ntrol valve. The cause of this event was a failed operational amplifier installed on circuit card that provided input to the Turbine Control System Channel 1.

Corrective actions include the replacement of the rate limiter circuit cards with re-furbished cards. Future corrective actions will include the implementation of a modification to replace the turbine control system with a digital control system. There were no actual nuclear safety consequences or radiological consequences during the event.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 22 of 132 NRC Code Mapped LER Number Event Date Abstract Code Description GGNS IE 4162016007 9/8/2016 QR6 Manual Technical Specification Shutdown Because of the Loss of the Residual Heat %T3A Reactor Removal Pump. On September 4, 2016 at 02:58, Grand Gulf Nuclear Station Trip entered three TS LCO Action Statements because RHR 'A' pump was declared inoperable. LCO Action Statements entered: 1) 3.5.1 for one low pressure ECCS injection/spray subsystem, 2) 3.6.1.7 for one RHR containment spray subsystem, and 3) 3.6.2.3 for one RHR suppression pool*cooling subsystem. All have 7 day Completion Times. A decision was made to shutdown the plant to repair the RHR 'A' pump because, based on the troubleshooting and testing plan, the pump could not be repaired and returned to service with the LCO Completion Times. At 0300 CDT on 09/08/16, GGNS initiated the transition to Mode 4. The Direct Cause was the pump's inability to develop a TS differential pressure of 131 psid. The Apparent Cause revealed defects in the manufacturing process which led to inter-column leakage; misalignment between rotating and stationary elements; and machined registered fits that

\

were out-of-tolerance. The failed pump was removed and sent to the vendor facility for failure analysis. A replacement pump was installed and tested satisfactorily. RHR 'A' was returned to operable.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 23 of 132 NRC Code Mapped LER Number Event Date Abstract Code Description GGNS IE 4162017003 4/4/2017 QR6 Manual Reactor Shutdown Because of Condensate System Inventory Depletion and a %T3B Reactor Manual Reactor Core Isolation Cooling (RCIC) Initiation Because of Feedwater Trip System Shutdown. At 00:10 on, April 4, 2017, the reactor was manually shutdown from approximately 75 percent core thermal power due to condensate storage tank level lowering to 24 feet. All control rods fully inserted and all systems actuated and operated as designed. No safety relief valves actuated. Reactor level and pressure were controlled within normal bands. Reactor core isolation cooling (RCIC) was manually initiated for level control. Decay heat was removed via steam discharge to the condenser, and to the suppression pool via RCIC. The electrical grid was stable and supplying plant loads. The cause of the condensate depletion was a condensate system leak. The condensate system leak was a failed pipe connection c~used by cycling water injection valves that induced excessive vibration on the pipe flange. A failing Turbine Control Card caused the faulty signals; which led to the water injection valves cycling. The piping and flange connection were repaired, and the Turbine Control Card was replaced. In addition, the Turbine Control System is planned to be replaced in Refueling Outage 22 in 2020. All other systems operated as designed, and there were no actual nuclear safety or radiological consequences during the event.

ENTG GGX083-RPT-001 Data Sensitivity Study Page 24 of 132 NRC Code Mapped LER Number Event Date Abstract Code Description GGNS IE 4162017006 8/29/2017 QR6 Manual Completion of Grand Gulf Nuclear Station Shutdown Requ'ired By Technical %T3A Reactor Specifications Because of an Inoperable A Residual Heat Removal Pump. On Trip August 22, 2017 at 2321 hours0.0269 days 0.645 hours 0.00384 weeks 8.831405e-4 months central daylight time, Grand Gulf Nuclear Station (GGNS) entered Technical Specification (TS) conditions for three Limiting Condition for Operations (LCOs) not met due to Residual Heat Removal 'A' system (RHR A) being declared inoperable. Entergy Operations Inc. (Entergy) made the decision to shut down the plant based on the results of troubleshooting performed on the RHR A pump. The A RHR pump TS differential pressure was out of specification (low) and could not be returned to acceptable limits. GGNS initiated plant shutdown as required by Technical Specifications 3.5.1, 3.6.1.7, and 3.6.2.3 at 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months CDT on August 29, 2017, due to expected restoration of RHR A exceeding the completion time of 7 days prior to restoring Operability. The shutdown was completed and entry into MODE 3 occurred at 2217 hours0.0257 days 0.616 hours 0.00367 weeks 8.435685e-4 months CDT on August 29, 2017. The direct cause of the event was increased surface roughness from corrosion in the Division I Residual Heat Removal Pump due to suppression pool water quality and lack of pump passivation. Corrective actions include replacement and successful testing of the pump, reanalysis of calculation limits, procedural upgrades, and the enhancement of pump management controls. This condition is reportable as a completion of a plant shutdown required by the TS.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 25 of 132 NRC Code Mapped LER Number Event Date Abstract Code Description GGNS IE 4162018001 1/30/2018 QR6 Manual Reactor Manual Shutdown due to Turbine Pressure Control Valve Position %T3A Reactor Changes. On January 30, 2018, Grand Gulf Nuclear Station (GGNS) was Trip operating in Mode 1 at 91% power and was in the process of increasing power. At 1739 hours0.0201 days 0.483 hours 0.00288 weeks 6.616895e-4 months CST on January 30, 2018, GGNS experienced main turbine control valve (TCV) position changes of between 3 and 5 percent and main generator output load changes of approximately 20 megawatts with a periodicity of approximately 3 seconds. At 1822 on January 30, 2018, operators performed a manual shut down of the reactor by moving the reactor mode switch from RUN to SHUTDOWN to place the unit in Mode 3.

Upon reactor shutdown all systems performed as designed and no subsequent safety system actuations occurred. The cause of the manual shutdown was

- conservative operator response to unanticipated main turbine generator output changes. Corrective actions include adjustments to the control circuit, and revision of work task documents for adjustment of the control circuits.

There were no consequences to the general safety of the public, nuclear safety, industrial safety and radiological safety for this event.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 26 of 132 Appendix B - Bayesian Update Worksheet for Initiating Events

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ENTG GGX083-RPT-001 Data Sensitivity Study Page 30 of 132 Appendix C - Unavailability Calculation

ENTGGGX083-RPT-001 Data Sensitivity Study Page 31 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 11 Cll-MDP-MA- STANDBY PUMP 620.75 88618.01 7.00E-3 Sheet Cll Hours" COOlA Cll-COOlA UNAVAILABLE DUE TO TEST OR MAINTENANCE 11 Cll-MDP-MA- STANDBY PUMP 380.33 88618.01 4.29E-3 Sheet Cll Hours" COOlB Cll-COOlB IS UNAVAILABLE DUE TO TEST OR ~

MAINTENANCE 11 C41-TRN-MA-TRNA SLC PUMP TRAIN A 341.99 88618.01 3.86E-3 Sheet C41 Hours" UNAVAILABLE DUE TO MAINTENANCE 11 11 C41-TRN-MA-TRNB SLC PUMP TRAIN B 410.99 88618.01 4.64E-3 Sheet C41 Hours UNAVAILABLE DUE TO MAINTENANCE 11 El2-TRN-MA-RHRA RHR TRAIN A 1097.78 105192.00 l.04E-2 Sheet E12 Hours" UNAVAILABLE DUE TO MAINTENANCE 11 El2-TRN-MA-RHRB RHR TRAIN B 607.90 105192.00 5.78E-3 Sheet E12 Hours" UNAVAILABLE DUE TO MAINTENANCE

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ENTGGGX083-RPT-001 Data Sensitivity Study Page 32 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 11 E12-TRN-MA-RHRC RHR TRAIN C 431.01 105192.00 4.lOE-3 Sheet El2 Hours" UNAVAILABLE DUE TO MAINTENANCE 11 E21-MDP-MA-C001 LPCS SYSTEM 286.78 105192.00 2.73E-3 Sheet E21, E22 Hours" UNAVAILABLE DUE TO TESTING/

MAINTENANCE E22-MOV-MA- TEST LINE IN 0.00 105192.00 O.OOE+OO There was no data provided F023 OPERATION--VALVE in sheet "E22 Hours" for this F023-C OPEN component. Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

E22-MOV-MA- TEST LINE IN 0.00 105192.00 O.OOE+OO There was no data provided FlOll OPERATION--VALVES in sheet "E22 Hours" for this FOlO-C & FOll-C component. Assume 005 OPEN time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 33 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 E22-SYS-MA-HPCS HPCS UNAVAILABLE 908.14 88618.01 1.02E-2 Sheet "E21, E22 Hours" DUE TO MAINTENANCE P81-DGN-MAlll- PS DIESEL GEN. 13 1251.43 88618.01 1.41E-2 Sheet "P75 Hours" DG13 OUT FOR MAINTENANCE E30-MOV-MA- SPMU TRAIN A 106.63 88618.01 1.20E-3 Sheet "E30 Hours" SPMUA VALVES UNAVAILABLE DUE J TO MAINTENANCE 11 E30-MOV-MA- SPMU TRAIN B 145.75 88618.01 1.64E-3

Sheet E30 Hours" SPMUB UNAVAILABLE DUE TO MAINTENANCE 11 E51-TDP-MA-C001 RCIC UNAVAILABLE 991.93 88618.01 l.12E-2 Sheet E51 Hours" DUE TO MAINTENANCE L20-BAT-MA-1H1 24V DC BATIERY 14.00 105192.00 l.33E-4 MCR GG-4962 There was no data provided 1Hl UNAVAILABLE for this system. _Assume DUE TO TEST OR 005 time is constant over MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 34 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L20-BAT-MA-1J 1 24V DC BATTERY lJl 14.00 105192.00 l.33E-4 MCR GG-4962 There was no data provided UNAVAILABLE DUE for this system. Assume TO TEST OR 005 time is constant over MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

L20-BAT-MA-1 H2 24V DC BATTERY 14.00 105192.00 1.33E-4 MCR GG-4962 There was no data provided 1H2 UNAVAILABLE for this system. Assume DUE TO TEST OR 005 time is constant over MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

L20-BAT-MA-1J2 24V DC BATTERY 1J2 14.00 105192.00 1.33E-4 MCR GG-4962 There was no data provided UNAVAILABLE DUE for this system. Assume TO TEST OR 005 time is constant over MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 35 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L50-BCC-MA-1 H4 BATTERY CHARGER 20.00 105192.00 1.90E-4 MCR GG-,4962 There was no data provided 1H4 UNAVAILABLE for this system. Assume DUE TO TEST OR 005 time is constant over MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

L50-BCC-MA-1J4 BATIERY CHARGER 20.00 105192.00 1.90E-4 MCR GG-4962 There was no data provided 1J4 UNAVAILABLE for this system. Assume DUE TO TEST OR 005 time is constant over MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

LSO-BCC-MA-1H5 BATTERY CHARGER 12.00 105192.00 l.14E-4 MCR GG-4962 There was no data provided lHS UNAVAILABLE for this system. Assume DUE TO TEST OR 005 time is constant over MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 36 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L50-BCC-MA-1J5 BATTERY CHARGER 12.00 105192.00 l.14E-4 MCR GG-4962 There was no data provided lJS UNAVAILABLE for this system. Assume DUE TO TEST OR OOS time is constant over MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

L51-BCC-MA-1A4 BATTERY CHARGER 0.00 105192.00 O.OOE+OO There was no data provided 11 1A4 UNAVAILABLE in sheet L51 Hours" for this DUE TO TEST OR comporent. Assume 005 MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

L51-BCC-MA-1D4 BATTERY CHARGER 0.00 105192.00 O.OOE+OO There was no data provided 11 1D4 UNAVAILABLE in sheet l51 Hours" for this DUE TO TEST OR component. Assume OOS MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 37 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 LSl-BCC-MA-lAS BATTERY CHARGER 0.00 105192.00 O.OOE+OO There was no data provided 1A5 UNAVAILABLE in sheet "L51 Hours" for this DUE TO TEST OR component. Assume OOS MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update

(

(105192/52608).

L51-BCC-MA-1D5 BATTERY CHARGER 0.00 105192.00 O.OOE+OO There was no data provided 1D5 UNAVAILABLE in sheet "L51 Hours" for this DUE TO TEST OR component. Assume OOS MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

L51-BCC-MA-1B4 BATTERY CHARGER b.oo 105192.00 O.OOE+OO There was no data provided 184 UNAVAILABLE in sheet "L51 Hours" for this DUE TO TEST OR component. Assume OOS MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 38 of 132 OOS Hours Exp. Hours

- T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L51-BCC-MA-1E4 BATTERY CHARGER 0.00 105192.00 O.OOE+OO There was no data provided 1E4 UNAVAILABLE in sheet "LSl Hours 11 for this DUE TO TEST OR component. Assume OOS MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

L51-BCC-MA-185 BATTERY CHARGER 0.00 105192.00 O.OOE+OO There was no data provided 185 UNAVAILABLE in sheet 11 L51 Hours" for this DUE TO TEST OR component. Assume OOS MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

L51-BCC-MA-1ES BATTERY CHARGER 0.00 105192.00 O.OOE+OO There was no data provided lES UNAVAILABLE in sheet "L51 Hours" for this DUE TO TEST OR component. Assume 005 MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 39 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L51-BCC-MA-1C4 BATTERY CHARGER 0.00 105192.00 O.OOE+OO There was no data provided 11 1C4 UNAVAILABLE in sheet L51 Hours" for this DUE TO TEST OR component. Assume OOS r

MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

L51-BCC-MA-1G4 BATTERY CHARGER 8.00 105192.00 7.60E-5 MCR GG-4962 There was no data provided 11 1G4 UNAVAILABLE in sheet LSl Hours" for this DUE TO TEST OR component. Assume 005 MAINTENANCE time is constant over time, so adjust by ratio of new

- exposure time to exposure time from last update (105192/52608).

. L51-BCC-MA-2G4 BATTERY CHARGER 8.00 105192.00 7.60E-5 MCR GG-4962 There was no data provided 11 2G4 UNAVAILABLE ~- in sheet LSl Hours" for this DUE TO TEST OR component. Assume 005 MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 40 of 132 OOS Hours Exp. Hours T/M, Original Rev. 4A Event Name Description 9/1/06- 9/1/06 - Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 LSl-BCC-MA-lCS BATTERY CHARGER . 0.00 105192.00 O.OOE+OO There was no data provided lCS UNAVAILABLE in sheet "LSl Hours" for this DUE TO TEST OR component. Assume OOS MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

LS l~BCC-MA-1 GS BATTERY CHARGER 12.00 105192.00 1.14E-4 MCR GG-4962 There was no data provided lGS UNAVAILABLE in sheet 11 LSl Hours" for this DUE TO TEST OR component. Assume 005 MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

L51-BCC-MA-2GS BATTERY CHARGER 14.00 105192.00 1.33E-4 MCR GG-4962 There was no data provided 2GS UNAVAILABLE in sheet "L51 Hours" for this DUE TO TEST OR component. Assume OOS MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

.ENTGGGX083-RPT-001 Data Sensitivity Study Page 41 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06 - 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L51-BCC-MA-1K4 BATTERY CHARGER 172.36 105192.00 1.64E-3 MCR GG-4962 There was no data provided 1K4 UNAVAILABLE in sheet 11 LSl Hours" for this DUE TO TEST OR component. Assume 005 MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

L51-B.CC-MA-1K5 BATIERY CHARGER 95.98 105192.00 9.12E-4 MCR GG-4962 There was no data provided 1K5 UNAVAILABLE in sheet 11 LSl Hours" for this DUE TO TEST OR - component. Assume 005 MAINTENANCE time is constant over time, so adjust by ratio of new exposure,time to exposure time from last update (105192/52608).

L51-BCC-MA-1L4 BATTERY CHARGER 93.98 105192.00 8.93E-4 MCR ~G-4962 There was no data provided 1L4 UNAVAILABLE in sheet "L51 Hours" for this DUE TO TEST OR component. Assume 005 MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTG GGX083-RPT-001 Data Sensitivity Study Page 42 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06 - 9/1/06- Sensitivity Case Notes Unavail. Notes I

8/31/18 8/31/18 LSl-BCC-MA-lLS BATTERY CHARGER 47.99 105192.00 4.56E-4 MCR GG-4962 There was no data provided lLS UNAVAILABLE in sheet "L51 Hours" for this DUE TO TEST OR component. Assume 005 MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

N19-MDP-MA- CONDENSATE 86.86 88618.01 9.SOE-4 There was no data provided C002A BOOSTER PUMP in sheet "N19 Hours" for N19-C002A this component. Assume UNAVAILABLE DUE OOS time is constant over TO MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

N19-MDP-MA- CONDENSATE 30.21 88618.01 3.41E-4 There was no data provided C002B BOOSTER PUMP in sheet "N19 Hours" for N19-C002B this component. Assume UNAVAILABLE DUE 005 time is constant over TO MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update {88618.01/46930).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 43 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail.- Notes 8/31/18 8/31/18 N19-MDP-MA- CONDENSATE 18.88 88618.01 2.13E-4 There was no data provided C002C BOOSTER PUMP in sheet "N19 Hours" for N19-C002C this component. Assume UNAVAILABLE DUE OOS time is constant over TO MAINTENANCE time, so adjust by ratio of

- new exposure time to exposure time from last update (88618.01/46930).

N19-MDP-MA- CONDENSATE PUMP 6.29 88618.01 7.lOE-5 There was no data provided C003A N19-C003A in sheet "N19 Hours" for UNAVAILABLE DUE this component. Assume TO MAINTENANCE 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last -

update (88618.01/46930).

N19-MDP-MA- CONDENSATE PUMP 6.29 88618.01 7.lOE-5 There was no data provided C003B N19-C003B in sheet "N19 Hours" for UNAVAILABLE DUE this component. Assume TO MAINTENANCE 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update {88618.01/46930).

Data Sensitivity Study ENTGGGX083-RPT-001 Page 44 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Description 9/1/06- 9/1/06- Sensitivity Case Notes Event Name Unavail. Notes 8/31/18 8/31/18 CONDENSATE PUMP 6.29 88618.01 7.10E-5 There was no data provided N19-MDP-MA-N19-C003C in sheet "Nl9 Hours" for C003C UNAVAILABLE DUE this compo-nent. Assume TO MAINTENANCE OOS time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

CFFF TRAIN A 66.09 88618.01 7.46E-4 There was no data provided N19-FLT-MA-CFFFA UNAVAILABLE DUE in sheet "N19 Hours" for TO MAINTENANCE this component. Assume OOS time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

CFFF TRAIN B 66.09 88618.01 7.46E-4 There was no data provided N19-FLT-MA-CFFFB UNAVAILABLE DUE in sheet "N19 Hours" for TO MAINTENANCE this component. Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 45 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 N19-FLT-MA-CFFFC CFFF TRAIN C 66.09 88618.01 7.46E-4 There was no data provided UNAVAILABLE DUE in sheet "N19 Hours" for TO MAINTENANCE this component. Assume 005 time is constant over time, so adjust by ratio of new exposure time to

- exposure time from last update (88618.01/46930).

N19-FLT-MA- CFFF TRAIN D 66.09 88618.01 7.46E There was no data provided CFFFD UNAVAILABLE DUE in sheet "N19 Hours" for TO MAINTENANCE this component. Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

N19-FLT-MA-TRNA DEMINERALIZER 66.09 88618.01 7.46E-4 There was no data provided TRAIN A in sheet "N19 Hours" for UNAVAILABLE DUE this component. Assume TO MAINTENANCE 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update {88618.01/46930}.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 46 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 N19-FLT-MA-TRNB DEMINERALIZER 66.09 88618.01 7.46E-4 There was no data provided TRAIN B in sheet "Nl9 Hours" for UNAVAILABLE DUE this component. Assume TO MAINTENANCE OOS time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

Nl9-FLT-MA-TRNC DEMINERALIZER 66.09 88618.01 7.46E-4 There was no data provided TRAIN C in sheet "N19 Hours" for UNAVAILABLE DUE this component. Assume TO MAINTENANCE OOS time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

N19-FLT-MA-TRND DEMINERALIZER 66.09 88618.01 7.46E-4 There was no data provided 11 TRAIN D - in sheet Nl9 Hours" for UNAVAILABLE DUE this component. Assume TO MAINTENANCE OOS time is constant over time, so adjust by ratio of new exposure time to exposure time from last update {88618.01/46930).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 47 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06 - 9/1/06- Sensitivity Case Notes Unavail. Notes

! 8/31/18 8/31/18 Nl9-FLT-MA-TRNE DEMINERALIZER 66.09 88618.01 7.46E-4 There was no data provided TRAIN E in sheet "N19 Hours" for UNAVAILABLE DUE this component. Assume TO MAINTENANCE OOS time .is constant over time>so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

N19-FLT-MA-TRNF DEMINERALIZER 66.09 88618.01 7.46E-4 There was no data provided 11 in sheet 11 N19 Hours for

~

TRAIN F UNAVAILABLE DUE this component. Assume TO MAINTENANCE OOS time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

Nl9-FLT-MA-TRNG DEMINERALIZER 66.09 88618.01 7.46E-4 There was no data pr~vided 11 TRAIN G in sheet N19 Hours" for UNAVAILABLE DUE this component. Assume TO MAINTENANCE 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 48 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 N19-FLT-MA-TRNH DEMINERALIZER 66.09 88618.01 7.46E-4 There was no data provided TRAIN H in sheet "N19 Hours" for UNAVAILABLE DUE this component. Assume TO MAINTENANCE . OOS time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

N19-HTX-MA- HEAT EXCHANGER 86.86 88618.01 9.80E-4 Assume same There was no data provided BOOlA N19-B001A unavailability as in sheet "N19 Hours" for UNAVAILABLE DUE respective this component. Assume TO MAINTENANCE condensate booster 005 time is constant over pump time, so a.djust by ratio of new exposure time to exposure time from last update (88618.01/46930).

N19-HTX-MA- HEAT EXCHANGER 30.21 88618.01 3.41E-4 Assume same There was no data provided I

80018 N19-B001B unavailability as in sheet "N19 Hours" for UNAVAILABLE DUE respective this component. Assume TO MAINTENANCE condensate booster 005 time is constant over pump time, so adjust by ratio of new exposure- time to exposure time from last update (88618.01/46930}.

ENTG GGX083-RPT-001 Data Sensitivity Study Page 49 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06 - 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18

(_

Nl9-HTX-MA- HEAT EXCHANGER 18.88 88618.01 2.13E-4 Assume same There was no data provided BOOlC N19-B001C unavailability as in sheet 11 N19 Hours" for UNAVAILABLE DUE respective this component. Assume TO MAINTENANCE condensate booster 005 time is constant over pump time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

N19-HTX-MA- HEAT EXCHANGER 86.86 88618.01 9.80E-4 Assume same There was no data provided B002A N19-B002A -- unavailability as 11 in sheet 11 N19 Hours for UNAVAILABLE DUE respective this component. Assume Tb MAINTENANCE condensate booster 005 time is constant over pump time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

N19-HTX-MA- HEAT EXCHANGER 30.21 88618.01 3.41E-4 Assume same There was no data provided 80028 N19-B002B unavailability as in sheet "N19 Hours" for UNAVAILABLE DUE respective this component. Assume TO MAINTENANCE condensate booster 005 time is constant over pump time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

Data Sensitivity Study ENTGGGX083-RPT-001 Page 50 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Description 9/1/06- 9/1/06- Sensitivity Case Notes Event Name Unavail. Notes 8/31/18 8/31/18 N19-HTX-MA- HEAT EXCHANGER 18.88 88618.01 2.13E-4 Assume same There was no data provided N19-B002C unavailabili ty as in sheet "N19.Hours" for B002C UNAVAILABLE DUE respective this component. Assume TO MAINTENANCE condensate booster 005 time is constant over pump time, so adjust by ratio of new exposure time to exposure time from last update {88618.01/46930).

N19-HTX-MA- HEAT EXCHANGER 86.86 88618.01 9.80E-4 Assume same There was no data provided 11 N19-B003A unavailabili ty as in sheet Nl9 Hours" for B003A UNAVAILABLE DUE respective this component. Assume TO MAINTENANCE condensate booster 005 time is constant over pump time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

Nl9-HTX-M A- HEAT EXCHANGER 30.21 88618.01 3.41E-4 Assume same There was no data provided N19-B003B unavailabili ty as in sheet "Nl9 Hours" for 80038 UNAVAILABLE DUE respective this component. Assume TO MAINTENANCE condensate booster 005 time is constant over pump time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 51 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 Nl9-HTX-MA- HEAT EXCHANGER 18.88 88618.01 2.13E-4 Assume same There was no data provided B003C N19-B003C unavailability as in sheet "Nl9 Hours" for UNAVAILABLE DUE respective this component. Assume TO MAINTENANCE condensate booster 005 time is constant over pump time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

N19-HTX-MA- HEAT EXCHANGER 86.86 88618.01 9.80E-4 Assume same There was no data provided 11 11 B004A N19-B004A unavailability as in sheet N19 Hours for UNAVAILABLE DUE respective this component. Assume TO MAINTENANCE condensate booster 005 time is constant over pump time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

Nl9-HTX-MA- HEAT EXCHANGER 30.21 88618.01 3.41E-4 Assume same There was no data provided 80048 N19-B004B unavailability as in sheet "Nl9 Hours" for UNAVAILABLE DUE respective this component. Assume TO MAINTENANCE condensate booster 005 time is constant over pump time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 52 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06 - Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 N19-HTX-MA- HEAT EXCHANGER 18.88 88618.01 2.13E-4 Assume same There was no data provided B004C N19-B004C unavailability as in sheet "N19 Hours" for UNAVAILABLE DUE respective this component. Assume TO MAINTENANCE condensate booster OOS time is constant over pump time, so adjust by ratio of

(

new exposure time to

\

exposure time from last update (88618.01/46930).

11 P41-CTS-MA- FAN P41-C003A 528.00 105192.00 5.02E-3 Per Sheet P41 Hours", each C003A UNAVAILABLE DUE SSW Fan accrues 44 hrs/yr TO MAINTENANCE 6os time (44 hrs/yr* 12 yrs

=528 hrs).

11 P41-CTS-MA- FAN P41-C0038 528.00 105192.00 5.02E-3 Per Sheet P41 Hours'1, each C003B UNAVAILABLE DUE SSW Fan accrues 44 hrs/yr TO MAINTENANCE 0,05 time (44 hrs/yr* 12 yrs

= 528 hrs).

P41-CTS-MA- FAN P41-C003C 528.00 105192.00 5.02E-3 Per Sheet "P41 Hours", each C003C UNAVAILABLE DUE SSW Fan accrues 44 hrs/yr TO MAINTENANCE 005 time (44 hrs/yr* 12 yrs

=528 hrs).

II P41-CTS-MA- FAN P41-C003D 528.00 105192.00 5.02E-3 ' Per Sheet P41 Hours", each C003D UNAVAILABLE DUE SSW Fan accrues 44 hrs/yr TO MAINTENANCE 005 time (44 hrs/yr* 12 yrs

= 528 hrs).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 53 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P41-TRN-MA- SSW TRAIN A 297.65 105192.00 2.83E-3 Sheet "P41 Hours"

~

SSW_A UNAVAILABLE DUE TO MAINTENANCE P41-TRN-MA- SSW TRAIN B 312.16 105192.00 2.97E-3 Sheet "P41 Hours" SSW_B UNAVAILABLE DUE TO MAINTENANCE P41-TRN-MA- SSW TRAIN C 491.35 88618.01 5.54E-3 Sheet "P41 Hours" ssw_c UNAVAILABLE DUE TO MAINTENANCE P42-MDP-MA- MOTOR DRIVEN 29.99 105192.00 2.85E-4 Zero functional There was no data provided 11 COOlA PUMP P42-C001A failures, planned in sheet P42, P43 and P47 UNAVAILABLE DUE maintenance only, 2 Hours" for this component.

TO MAINTENANCE out of 3 pumps are Assume 005 time is normally operating constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608}.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 54 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P42-MDP-MA- MOTOR DRIVEN 33.99 105192.00 3.23E-4 Zero functional There was no data provided COOlB PUMP COOlB failures, planned in sheet "P42, P43 and P47 UNAVAILABLE DUE maintenance only, 2 Hours" for this component.

TO MAINTENANCE out of 3 pumps are Assume OOS time is normally operating constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

P42-MDP-MA- MOTOR DRIVEN 29.99 105192.00 2.85E-4 Zero functional There was no data provided COOlC PUMP COOlC failures, planned in sheet "P42, P43 and P47 UNAVAILABLE DUE maintenance only, 2 Hours 11 for this component.

TO MAINTENANCE out of 3 pump*s are Assume OOS time is normally operating constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 55 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06 - Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P42-HTX-MA- HEAT EXCHANGER 29.99 105192.00 2.85E-4 Zero functional There was no data provided BOOlA P42-B001A failures, 2 out of 3 in sheet "P42, P43 and P4 7 UNAVAILABLE DUE heat exchangers are Hours" for this component.

TO MAINTENANCE normally operating, Assume 005 time is assume same UA as constant over time, so

~

pumps adjust by ratio of new exposure time to exposure time from last update (105192/52608).

P42-HTX-MA- HEAT EXCHANGER 33.99 105192.00 3.23E-4 Zero functional There was no data provided 80018 P42-B001B failures, _2 out of 3 in sheet "P42, P43 and P47 UNAVAILABLE DUE heat exchangers are Hours" for this component.

TO MAINTENANCE normally operating, Assume OOS time is assume same UA as constant over time, so pumps adjust by ratio of new exposure time to exposure

~

time from last update (105192/52608).

ENTG GGX083-RPT-001 Data Sensitivity Study Page 56 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06 - 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P42-HTX-MA- HEAT EXCHANGER 29.99 105192.00 2.SSE-4 Zero functional There was no data provided BOOlC P42-B001C failures, 2 out of 3 in sheet "P42, P43 and P47 UNAVAILABLE DUE heat exchangers are Hours" for this component.

TO MAINTENANCE normally operating, Assume OOS time is assume same UA as constant over time, so -

pumps adjust by ratio of new exposure time to exposure time from last update (105192/52608).

P43-HTX-MA- HEAT EXCHANGER 1072.56 88618.01 1.21E-2 Zero functional There was no data provided II B001A B001A UNAVAILABLE failures, 2 out of 3 in sheet P42, P43 and P4 7 DUE TO heat exchangers are Hours" for this component.

MAINTENANCE normally operating; Assume OOS time is estimate of planned constant over time, so maintenance hrs adjust by ratio of new seems very high exposure time to exposure time from last update (88618.01/469 30).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 57 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- ~

Sensitivity Case Notes Unavail.

Notes 8/31/18 8/31/18 P43-HTX-MA- HEAT EXCHANGER 923.38 88618.01 l.04E-2 Zero functional There was no data provided 80018 80018 UNAVAILABLE failures, 2 out of 3 in sheet "P42, P43 and P47 DUE TO heat exchangers are Hours" for this component.

MAINTENANCE normally operating; Assume OOS time is estimate of planned constant over time, so maintenance hrs adjust by ratio of new seems very high exposure time to exposure time from last update (88618. 01/46930).

P43-HTX-MA- HEAT EXCHANGER 1049.90 88618.01 l.18E-2 Zero functional There was no data provided BOOlC BOOlC UNAVAILABLE failures, 2 out of 3 in sheet II P42, P43 and P4 7 DUE TO heat exchangers are Hours" for this component.

MAINTENANCE normally operating; Assume 005 time is estimate of planned constant over time, so maintenance hrs adjust by ratio of new seems very high exposure time to exposure time from last update (88618.01/46930}.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 58 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P43-MDP-MA- MOTOR DRIVEN 77.42 88618.01 8.74E-4 Zero functional There was no data provided 11 C001A PUMP C001A OUT failures, 2 out of 3 in sheet P42, P43 and P47 DUE TO pumps are normally Hours" for this component.

MAINTENANCE operating Assume 00.S time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

P43-MDP-MA- MOTOR DRIVEN 107.63 88618.01 1.21E-3 Zero functional There was no data provided COOlB PUMP COOlB OUT failures, 2 out of 3 in sheet "P42, P43 and P47 DUE TO pumps are normally Hours" for this component.

MAINTENANCE operating Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

ENTGGGX083-RPT-001 Data Sensitivity Study ,

Page 59 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06 - 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P43-MDP-MA- MOTOR DRIVEN 173.72 88618.01 1.96E-3 Zero functional There was no data provided COOlC PUMP C001C OUT failures, 2 out of 3 in sheet II P42, P43 and P4 7 DUE TO pumps are normally Hours" for this component.

MAINTENANCE operating Assume OOS time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

P47-WEL-MA- RADIAL WELL 1 - 105192.00 l.OOE+OO Some of the radial Changed to 1.0; see Note 3 WELLl UNAVAILABLE DUE well UA hours seem of Table 13 of the DA TO MAINTENANCE very high; possibly Notebook.

adding standby time to maintenance time

ENTG GGX083-RPT-001 Data Sensitivity Study Page 60 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes lJnavail. Notes 8/31/18 8/31/18 P47-WEL-MA- - RADIAL WELL 3 15778.40 105192.00 1.SOE-1 Some of the radial There was no data provided WELL3 UNAVAILABLE DUE well UA hours seem in sheet "P42, P43 and P47 TO MAINTENANCE very high; possibly Hours" for this component.

~

adding standby time Assume 005 time is to maintenance time constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

P47-WEL-MA- RADIAL WELL 4 0.00 105192.00 O.OOE+OO Some of the radial There was no data provided WELL4 UNAVAILABLE DUE well UA hours seem in sheet "P42, P43 and P47 TO MAINTENANCE very high; possibly Hours" for this component.

adding standby time Assume OOS time is to maintenance time constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608). Since the original analysis had zero (0) 005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months for this radial well, the note in column G is not applicable, and can be removed.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 61 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P47-WEL-MA- RADIAL WELL 5 15778.40 105192.00 1.SOE-1 Some of the radial There was no data provided WELLS UNAVAILABLE DUE well UA hours seem in sheet "P42, P43 and P47 TO MAINTENANCE very high; possibly Hours" for this component.

adding standby time Assume OOS time is to maintenance time constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

P47-WEL-MA- RADIAL WELL 6 0.00 105192.00 O.OOE+OO Some of the radial There was no data provided WELL6 UNAVAILABLE DUE well UA hours seem in sheet II P42, P43 and P4 7 TO MAINTENANCE very high; possibly Hours" for this component.

adding standby time Assume OOS time is to maintenance time constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608). Since the original analysis had zero (0) 005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months for this radial well, the note in column G is not applicable, and can be removed.

ENTGGGX083-RPT-001 Data Sensitivity Study

Page 62 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P47-MDP-MA- RADIAL WELL PUMP 7342.40 105192.00 6.98E-2 MCR GR-4904 There was no data provided COOlA P47-C001A in sheet "P42, P43 and P47 UNAVAILABLE DUE Hours". The UA was TO MAINTENANCE entered as a constant, and the OOS time was calculated as the UA

Exposure hours.

Assume this is still valid.

P47-MDP-MA- RADIAL WELL PUMP 409.20 105192.00 3.89E-3 MCR GR-4904 There was no data provided COOlB P47-C001B in sheet "P42, P43 and P47 UNAVAILABLE DUE Hours". The UA was TO MAINTENANCE entered as a constant, and the 005 time was calculated 0 as the UA

Exposure hours.

Assume this is still valid.

P47-MDP-MA- RADIAL WELL PUMP 150.42 105192.00 l.43E-3 MCR GR-4904 There was no data provided COOlC P47-C001C in sheet "P42, P43 and P47 UNAVAILABLE DUE- Hours". The UA was TO MAINTENANCE entered as a constant, and the OOS time was calculated as the UA

Exposure hours.

Assume this is still valid.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 63 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P47-MDP-MA- RADIAL WELL PUMP 591.18 105192.00 5.62E-3 MCR GR-4904 There was no data provided COOlD P47-C001D in sheet "P42, P43 and P47 UNAVAILABLE DUE Hours". The UA was TO MAINTENANCE entered as a constant, and the 005 time was calculated as the UA

Exposure hours.

Assume this is still valid.

P47-MDP-MA- RADIAL WELL PUMP 15.57 105192.00 l.48E-4 MCR GR-4904 There was no data provided COOlE P47-C001E in sheet "P42, P43 and P47 UNAVAILABLE DUE Hours". The UA was TO MAINTENANCE entered as a constant, and the 005 time was calculated as the UA

Exposure hours.

Assume this is still valid.

P47-MDP-MA- RADIAL WELL PUMP 7.84 ' 105192.00 7.45E-5 MCR GR-4904 There was no data provided COOlF P47-C001F in sheet "P42, P43 and P47 UNAVAILABLE DUE Hours". The UA was TO MAINTENANCE entered as a constant, and the OOS time was calculated as the UA

Exposure hours.

Assume this is still valid.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 64 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06 - 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P47-MDP-MA- RADIAL WELL PUMP 499.66 105192.00 4.75E-3 MCR GR-4904 There was no data provided COOlJ P47-C001J in sheet "P42, P43 and P47 UNAVAILABLE DUE Hours". The UA was TO MAINTENANCE entered as a constant, and the 005 time was calculated as the UA

Exposure hours.

Assume this is still valid.

P47-MDP-MA- RADIAL WELL PUMP 1798.78 105192.00 1.71E-2 MCR GR-4904 There was no data provided 11 COOlK P47-C001K in sheet P42, P43 and P47 UNAVAILABLE DUE Hours". The UA was TO MAINTENANCE entered as a constant, and the 005 time was calculated as the UA

Exposure hours.

Assume this is still valid.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 65 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description* 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P47-MDP-MA- RADIAL WELL PUMP 14.19 54792.00 2.59E-4 MCR GR-4904 Original analysis stated COOlL P47-C001L pumps Land M were put

\

UNAVAILABLE DUE into service on June 1, 2012.

TO MAINTENANCE Between 6/1/12 and 8/31/2018 there are 54,792 hours0.00917 days 0.22 hours 0.00131 weeks 3.01356e-4 months . There was no data provided in sheet "P42, P43 and P47 Hours". The UA was*entered as a constant, and the 005 time was -

calculated as the UA

Exposure hours. Assume this is still valid.

P47-MDP-MA- RADIAL WELL PUMP 0.00 54792.00 O.OOE+OO MCR GR-4904 Original analysis stated COOlM P47-C001M pumps Land M were put UNAVAILABLE DUE into service on June 1, 2012.

TO MAINTENANCE Between 6/1/12 and 8/31/2018 there are 54,792 hours0.00917 days 0.22 hours 0.00131 weeks 3.01356e-4 months . There was no data provided in sheet "P42, P43 and P47 Hours". The UA was entered as a constant,

and the 005 time was calculated as the UA * ~

Exposure hours. Assume this is still valid.

ENTGGGX083-RPT-001 Dat~ Sensitivity Study Page 66 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P4 7-M CS-MA- WELL 1 AIR 34082.21 105192.00 3.24E-1 MCR GR-4904 There was no data provided C002A COMPRESSOR P47- in sheet "P42, P43 and P47 C002A UNAVAi LABLE Hours 11

The UA was DUE TO entered as a constant, and MAINTENANCE the OOS time was calculated as the UA

Exposure hours.

Assume this is still valid.

P47-MCS-MA- WELL 1 AIR 1441.13 105192.00 1.37E-2 MCR GR-4904 There was no data provided C002B COMPRESSOR P47- in sheet "P42, P43 and P47 C002B UNAVAILABLE Hours". The UA was DUE TO entered as a constant, and MAINTENANCE the 005 time was calculated as the UA

Exposure hours.

Assume this is still valid.

P47-MCS-MA- WELL 3 AIR 183.03 105192.00 1.74E-3 MCR GR-4904 There was no data provided C002C COMPRESSOR P47- in sheet "P42, P43 and P47 C002C UNAVAi LAB LE Hours". The UA was DUE TO entered as a constant, and MAINTENANCE the OOS time was calculated as the UA

Exposure hours.

Assume this is still valid.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 67 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06'- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P47-MCS-MA- WELL 3 AIR 409.20 105192.00 3.89E-3 MCR GR-4904 There was no data provided C002D COMPRESSOR P47- in sheet "P42, P43 and P47 C002D UNAVAILABLE Hours". The UA was DUE TO entered as a constant, and MAINTENANCE the 005 time was calculated as the UA

Exposure hours.

Assume this is still valid.

1 P47-MCS-MA- WELL 5 AIR 119.92 105192.00 l.14E-3 MCR GR-4904 There was no data provided C002E COMPRESSOR P47- in sheet "P42, P43 and P47 C002E UNAVAILABLE Hours". The UA was DUE TO entered as a constant, and MAINTENANCE the 005 time was calculated as the UA

Exposure hours.

Assume this is still valid.

P47-MCS-MA- WELL 5 AIR 64.06 105192.00 6.09E-4 MCR GR-4904 There was no data provided C002F COMPRESSOR P47- in sheet "P42, P43 and P47 C002F UNAVAILABLE Hours". The UA was DUE TO entered as a constant, and MAINTENANCE the 005 time was calculated as the UA

Exposure hours.

Assume this is still valid.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 68 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P47-MCS-MA- WELL4AIR 30400.49 105192.00 2.89E-1 MCR GR-4904 There was no data provided C002J COMPRESSOR P47- in sheet "P42, P43 and P47 C002J UNAVAILABLE . Hours". The UA was DUE TO entered as a constant, and MAINTENANCE the 005 time was calculated as the UA

Exposure hours.

Assume this is still valid.

P47-MCS-MA- WELL4AIR 275.60 105192.00 2.62E-3 MCR GR-4904 There was no data provided 11 C002K COMPRESSOR P47- in sheet P42, P43 and P47 C002K U NAVAi LAB LE Hours". The UA was DUE TO entered as a constant, and MAINTENANCE the 005 time was calculated as the UA

Exposure hours.

Assume this is still valid.

P51-MDC-MA- AIR COMPRESSOR 1172.17 78888.00 1.49E-2 78,888 exposure hours COOlA COOlA UNAVAILABLE based on time from Sept DUE TO 2009 until August 2018. No MAINTENANCE data in PSl.xls for compressors for August 2018. Assume average for each month over the entire period for this month.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 69 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06 - 9/1/06- Sensitivity Case Notes Unavail. 'Notes 8/31/18 8/31/18 PSl-MDC-MA- AIR COMPRESSOR 705.32 78888.00 8.94E-3 78,888 exposure hours COOlB COOlB UNAVAILABLE based on time from Sept DUE TO 2009-until August 2018. No

. MAINTENANCE data in PSl.xls for compressors for August 2018. Assume average for each month over the entire period for this month.

PSl-MDC-MA- AIR COMPRESSOR 2508.03 105192.00 2.38E-2 No data in PSl.xls for COOlC C001C UNAVAILABLE compressors for August DUE TO 2018. Assume average for MAINTENANCE each month over the entire period for this month.

PSl-DRY-MA-DRYA PLANT AIR DRYER A 936.03 105192.00 8.90E-3 Original data had O hours SKID OUT FOR even though Sheet "P51 MAINTENANCE Hours" included UA time.

P51-DRY-MA-DRYB PLANT AIR DRYER B 882.36 105192.00 8.39E-3 Original data had O hours SKID OUT FOR even though Sheet "P51 MAINTENANCE Hours" included UA time.

11 P64-E NG-MA- FIREWATER MOTOR 640.36 105192.00 6.09E-3 Sheet P64 Hours" TRNA DRIVEN PUMP TRAIN UNAVAILABLE DUE TO MAINTENANCE

ENTGGGX083-RPT-001 Data Sensitivity Study Page 70 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06 -,- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P64-E NG-MA-TRN B FIREWATER DIESEL 761.35 105192.00 7.24E-3 Sheet "P64 Hours" DRIVEN PUMP TRAIN AOUT FOR MAINTENANCE P64-MDP-MA- FIREWATER DIESEL 341.78 105192.00 3.25E-3 Sheet "P64 Hours" C002N DRIVEN PUMP TRAIN BOUT FOR MAINTENANCE P64-AOV-MA-TR1 AIR OPERATED 0.00 105192.00 O.OOE+OO There was no data provided VALVE TRAIN 1 in sheet "P64 Hours" for this UNAVAILABLE DUE component. Assume OOS TO MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

P64-AOV-MA-TR2 AIR OPERATED 0.00 105192.00 O.OOE+OO There was no data provided VALVE TRAIN 2 in sheet "P64 Hours" for this UNAVAILABLE DUE component. Assume OOS TO MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTG GGX083-RPT-001 Data Sensitivity Study Page 71 of 132 005 Hours Exp.'Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 P64-MOV-MA- MOTOR-OPERATED 0.00 105192.00 O.OOE+OO There was no data provided FAlOA VALVE FAlOA in sheet 11 P64 Hours" for this UNAVAILABLE DUE component. Assume 005 TO MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

P64-MOV-MA- MOTOR-OPERATED 0.00 105192.00 O.OOE+OO There was no data provided FA10B VALVE FAlOB in sheet 11 P64 Hours 11 for this UNAVAILABLE DUE component. Assume OOS TO MAINTENANCE time is constant over time, r_

so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

P71-CHR-MA- PLANT CHILLER P71- 3961.80 105192.00 3.77E-2 There was no data provided BOOlA B001A UNAVAILABLE in sheet 11 P71 Hours" for this DUE TO component. Assume OOS MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update

\ (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 72 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 -- -

P71-CHR-MA- PLANT CHILLER P71- 39219.11 105192.00 3.73E-1 There was no data provided BOOlB 80018 UNAVAILABLE in sheet "P71 Hours" for this DUE TO component. Assume OOS MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure

___,, time from last update (105192/52608).

P71-CHR-MA- PLANT CHILLER P71- 30289.09 105192.00 2.88E-1 There was no data provided 11 BOOlC BOOlC UNAVAILABLE in sheet P71 Hours" for this DUE TO ~

component. Assume OOS MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

P75-DGN-MA- PS DIESEL GEN. 11 1540.65 105192.00 1.46E-2 Sheet 11 P75 Hours" DGll OUT FOR MAINTENANCE 11 P75-DGN-MA- PS DIESEL GEN. 12 1693.42 105192.00 l.61E-2 Sheet P75 Hours" DG12 OUT FOR MAINTENANCE

ENTGGGX083-RPT-001 Data Sensitivity Study Page 73 of 132 OOS Hours Exp. Hours

-- T/M Original Rev. 4A Event Name Description 9/1/06 - 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 -

R27-BAC-MA-EAST AC BUS EAST 0.00 105192.00 O.OOE+OO MCR GG-4908 There was no data provided UNAVAILABILE DUE in sheet "R27 Hours" for this TO MAINTENANCE component. In the original analysis, the generic unavailability for busses documented in MCR GG-4908 was determined to not be applicable to switchyard buses. Changed to 0.0; see Note 2 of Table 13 of the DA Notebook. This is assumed to be still applicable.

R27-BAC-MA-WEST AC BUS WESJ 0.00 105192.00 0.00E+OO MCR GG-4908 There was no data provided 11 UNAVAILABILE DUE in sheet R27 Hours" for this TO MAINTENANCE component. In the original analysis, the generic unavailability for busses documented in MCR GG-4908 was determined to not

- be applicable to switchyard buses. Changed to 0.0; see Note 2 of Table 13 of the DA

- Notebook. This is ssumed to be still applicable.

ENTG GGX083-RPT-001 Data Sensitivity Study Page 74 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name ,oescription 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 R27-TAC-MA- BAXTER WILSON 5.87 105192.00 5.58E-5 MCR GG-4908 There was no data provided BAXWL LINE OUT OF in sheet "R27 Hours" for this SERVICE component. Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

R27-TAC-MA- FRANKLIN LINE OUT 461.89 105192.00 4.39E-3 MCR GG-4908 There was no data provided FRANK OF SERVICE in sheet "R27 Hours" for this component. Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update

~

(105192/52608).

R27-TAC-MA- PORT GIBSON LINE 13.00 105192.00 l.24F4 MCR GG-4908 There was no data provided PORTG OUT OF SERVICE in sheet "R27 Hours" for this component. Assume OOS time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 75 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 T51-CLU-MA- FAN COOLER 19.94 105192.00 1.90E-4 Sheet "TSl Hours" BOOlA T51B001-A UNAVAILABLE DUE TO MAINTENANCE T51-CLU-MA- FAN COOLER 53.60 105192.00 5.lOE-4 Sheet "T51 Hours" B002A TS1B002-A UNAVAILABLE DUE TO MAINTENANCE T51-CLU-MA- FAN COOLER 47.99 105192.00 4.56E-4 There was no data provided 11 B003A T518003-A in sheet T51 Hours" for this UNAVAILABLE DUE component. Assume 005 TO MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

T51-CLU-MA- FAN COOLER 47.99 105192.00 4.56E-4 There was no data provided 80048 T51B004-B in sheet "T51 Hours" for this UNAVAILABLE DUE component. Assume 005 TO MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 76 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes

~/31/18 8/31/18 T51-CLU-MA- FAN COOLER 47.99 105192.00 4.56E-4 There was no data provided BOOSB TSlBOOS-B in sheet "T51 Hours" for this UNAVAILABLE DUE component. Assume OOS TO MAINTENANCE time is constant over time, so adjust by- ratio of new exposure time to exposure time from last update (105192/52608).

T51-CLU-MA- FAN COOLER 47.99 105192.00 4.56E-4 There was no data provided B006A T51B006-A in sheet 11 T51 Hours" for this UNAVAILABLE DUE component. Assume 005 TO MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

T51-CLU-MA- FAN COOLER 47.99 1 105192.00 4.56E-4 There was no data provided B007A T51B007A in sheet "T51 Hours" for this UNAVAILABLE DUE component. Assume 005 TO MAINTENANCE time is constant over time, so adjust by ratio of new exposure ti~e to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 77 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06 - 9/1/06 - Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 T51-CLU-MA- FAN COOLER 47.99 105192.00 4.56E-4 There was no data provided 80078 TS1B007B in sheet "T51 Hours" for this UNAVAILABLE DUE component. Assume OOS TO MAINTENANCE time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

X77-DGN-MA- DIV I X77 SYSTEM 16.05 105192.00 1.53E-4 Sheet "X77, Y47 Hours" DG1RM UNAVAILABLE (PLANNED &

UNPLANNED)

X77-DGN-MA- DIV 11 X77 SYSTEM 3.85 105192.00 3.66E-5 Sheet "X77, Y47 Hours" DG2RM UNAVAILABLE (PLANNED &

UNPLANNED)

X77-DGN-MA- DIV Ill HPCS X77 24.10 105192.00 2.29E-4 Sheet "X77, Y47 Hours" DG3RM SYSTEM UNAVAILABLE (PLANNED &

UNPLANNED)

Y47-FNS-MA- SUBSYSTEM 1Y47- 90.56 105192.00 8.61E-4 Sheet "X77, Y47 Hours" COlAA COOlA UNAVAILABLE DUE TO TEST OR MAINTENANCE

ENTGGGX083-RPT-001 Data Sensitivity Study Page 78 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 Y4 7-FNS-MA- SUBSYSTEM 2Y47- 169.02 105192.00 1.61E-3 Sheet "X77, Y47 Hours" COlAB COOlA UNAVAILABLE Note that there is a large DUE TO TEST OR increase in the planned MAINTENANCE unavailability resulting in a 122% increase when compared to the prior analysis.

Y47-FNS-MA- SUBSYSTEM 1Y47- 139.79 88618.01 1.58E-03 Sheet "X77, Y47 Hours" COlBB COOlB UNAVAILABLE DUE TO TEST OR MAINTENANCE 277-TRN-MA- SSBRVS TRAIN A 331.66 105192.00 3.15E-3 There was no data provided SS BRA EQUIPMENT for this system. Assume UNAVAILABLE DUE 005 time is constant over TO MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

Z77-TRN-MA- SSBRVS TRAIN B 1875.23 105192.00 1.78E-2 Therewas no data provided SSBRB EQUIPMENT for t_his system. Assume UNAVAILABLE DUE OOS time is constant over .

TO MAINTENANCE time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 7'} of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes

- 8/31/18 8/31/18 L62-INV-MA-1Y80 125 V DC/120 V AC 85.92 88618.01 9.70E-4 A CR search was There was no data provided INVERTER 1Y80 performed to find any for this system. Assume UNAVAILABLE FOR occurrences of OOS time is constant over MAINTENANCE inverter time, so adjust by ratio of unavailability. The new exposure time to results were then exposure time from last checked to count only update (88618.01/46930).

the events that were relevant to the failure mode (test/maintenance 005 or failure to switch to alt DC source). The start and finish times for several WO's related to the relevant events were used to develop an average time which was applied to

'- all events.

l

ENTGGGX083-RPT-001 Data Sensitivity Study Page 80 of 132 OOS Hours Exp. Hours *-

T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L62-INV-MA-1Y82 125 V DC/120 V AC 85.92 88618.01 9.70E-4 A CR search was There was no data provided INVERTER 1Y82 performed to find any for this system. Assume UNAVAILABLE FOR occurrences of OOS time is constant over MAINTENANCE inverter time, so-adjust by ratio of unavailability. The new exposure time to results were then exposure time from last checked to count only update (88618.01/46930).

the events that were relevant to the failure mode (test/maintenance 005 or failure to switch to alt DC source). The start and finish times for several WO's related to the relevant events were used to develop an average time which was applied to all events.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 81 of 132 005 Hours Exp. Hours T/M Original Rev. 4A

Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L62-INV-MA-1Y87 125 V DC/120 V AC 85.92 88618.01 9.70E-4 A CR search was There was no data provided INVERTER 1Y87 performed to find any for this system. Assume UNAVAILABLE FOR occurrences of OOS time is constant over MAINTENANCE inverter time, so adjust by ratio of unavailability. The new exposure time to results were then exposure time from last checked to count only update {88618.01/46930).

the events that were relevant to the failure mode (test/maintenance 005 or failure to switch to alt DC source). The start and finish times for several WO's related to the relevant events were used to develop an average time which was applied to all events.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 82 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L62-INV-MA-1Y88 125 V DC/120 V AC 85.92 88618.01 9.70E-4 A CR search was There was no data provided INVERTER 1Y88 performed to fi._nd any for this system. Assume UNAVAILABLE FOR occurrences of OOS time is constant over MAINTENANCE inverter time, so adjust by ratio of unavailability. The new exposure time to results were then exposure time from last checked to count only update (88618.01/46930}.

\ the events that were relevant to the failure mode (test/maintenance 005 or failure to switch to alt DC source). The start and finish times for several WO's related to the relevant events were used to develop an average time which was applied to all events.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 83 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L62-INV-MA-1Y95 125 V DC/120 V AC 85.92 88618.01 9.70E-4 A CR search was There was no data provided INVERTER 1Y95 performed to find any for this system. Assume UNAVAILABLE FOR occurrences of OOS time is constant over MAINTENANCE inverter time, so adjust by ratio of unavailability. The new exposure time to results were then exposure time from last checked to count only update (88618.01/46930).

the events that were relevant to the failure mode (test/maintenance OOS or failure to switch to alt DC .J source). The start and finish times for

. several WO's related to the relevant events were used to develop an average time which was applied to all events.

ENTG GGX083-RPT-001 Data Sensitivity Study Page 84 of 132 005 Hours Exp. Hours T/M . Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L62-INV-MA-1 Y96 125 V DC/120 V AC 85.92 88618.01 9.70E-4 A CR search was There was no data provided INVERTER 1Y96 performed to find any for this system. Assume UNAVAILABLE FOR occurrences of 005 time is constant over MAINTENANCE inverter time, so adjust by ratio of unavailability. The new exposure time to results were then exposure time from last checked to count only update (88618.01/46930).

the events that were relevant to the failure mode (test/maintenance 005 or failure to switch to alt DC source). The start and finish times for several WO's related to the relevant events were used to develop an average time

- which was applied to all events.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 85 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 L62-INV-MA-1 Y99 125 V DC/120 V AC 85.92 88618.01 9.70E-4 A CR search was There was no data provided INVERTER 1Y99 performed to find any for this system. Assume UNAVAILABLE DUE occurrences of OOS time is constant over TO MAINTENANCE inverter time, so adjust by ratio of unavailability. The new exposure time to results were then exposure time from last checked to count only update (88618.01/46930).

the events that were relevant to the failure

\_ mode (test/maintenance 005 or failure to switch to alt DC source). The start and finish times for several WO's related to the relevant events were used to develop an average time which was applied to all events.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 86 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 E61-ANA-MA-DIV1 TRAIN A HYDROGEN 2304.00 105192.00 2.19E-2 Assume 8 tests/yr., 24 There was no data provided ANALYZERS hrs. per test, based on for this system. Assume UNAVAILABLE DUE testing procedure and same 8 tests/yr., 24 hrs;per TO MAINTENANCE engineering estimate test as prior assumption of average duration using 12 years.

E61-ANA-MA-DIV2 TRAIN B HYDROGEN 2304.00 105192.00 2.19E-2 Assume 8 tests/yr., 24 There was no data provided ANALYZERS hrs. per test, based on for this system. Assume UNAVAILABLE DUE testing procedure and same 8 tests/yr., 24 hrs. per TO MAINTENANCE engineering estimate test as prior assumption of average duration using 12 years.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 87 of 132 OOS Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06 - 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 -

E61-IGN-MA-DIV1 DIV I HYDROGEN 24.00 105192.00 2.28E-4** The Hydrogen igniters There was no data provided IGNITERS are tested four times for this system. Assume UNAVAILABLE DUE per year. According same as prior assumption TO MAINTENANCE to Work Orders, each using 12 years (0.5 hr/train-test takes about one test

4 train-test/yr* 12 yr

~

hour for both trains. =24 hr).

The total out of

- service time during the update period was 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (12 hrs per train).

ENTGGGX083-RPT-001 Data Sensitivity Study Page 88 of 132 005 Hours Exp. Hours T/M Original Rev. 4A Event Name Description 9/1/06- 9/1/06- Sensitivity Case Notes Unavail. Notes 8/31/18 8/31/18 E61-IGN-MA-DIV2 DIV II HYDROGEN 24.00 105192.00 2.28E-4 The Hydrogen igniters There was no data. provided IGNITERS are tested four times for this system. Assume UNAVAILABLE DUE per year. According same as prior assumption TO MAINTENANCE to Work Orders, each using 12 years (0.5 hr/train-test takes about one test

4 tra.in-test/yr

12 yr hour for both trains. =24 hr).

The total out of service time during the update period was 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (12 hrs per train). The

(

required service time was 52560.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 89 of 132 Appendix D - Flag File UA.txt

ENTGGGX083-RPT-001 Data Sensitivity Study Page 90 of 132 Cll-MDP-MA-COOlA PROB 0.00700478379056357 Cll-MDP-MA-COOlB PROB 0.00429182510417465 C41-TRN-MA-TRNA PROB 0.00385911020419732 C41-TRN-MA-TRNB PROB 0.00463773296947945 E12-TRN-MA-RHRA PROB 0.0104359932314244 E12-TRN-MA-RHRB PROB 0.00577895657464446 E12-TRN-MA-RHRC PROB 0.00409739333789642 E21-MDP-MA-C001 PROB 0.00272625231323037 E22-MOV-MA-F023 PROB O E22-MOV-MA-F1011 PROB O E22-SYS-MA-HPCS PROB 0.0102478002684398 E30-MOV-MA-SPMUA PROB 0.00120327185991071 E30-MOV-MA-SPMUB PROB 0.00164472674830513 ESl-TDP-MA-COOl PROB 0.0111932897913942 E61-ANA-MA-DIV1 PROB 0.0219028062970568 E61-ANA-MA-DIV2 PROB 0.0219028062970568 E61-IGN-MA-DIV1 PROB 0.000228154232261008 E61-IGN-MA-DIV2 PROB 0.000228 L20-BAT-MA-1Hl PROB 0.000133059610705596 L20-BAT-MA-1H2 PROB 0.000133059610705596 L20-BAT-MA-1Jl PROB 0.000133059610705596 L20-BAT-MA-1J2 PROB 0.000133059610705596 L50-BCC-MA-1H4 PROB 0.000190085158150852 LSO-BCC-MA-lHS PROB 0.000114051094890511 L50-BCC-MA-1J4 PROB 0.000190085158150852 LSO-BCC-MA-lJS PROB 0.000114051094890511 L51-BCC-MA-1A4 PROB O LSl-BCC-MA-lAS PROB O L51-BCC-MA-1B4 PROB O LSl-BCC-MA-lBS PROB O L51-BCC-MA-1C4 PROB O LSl-BCC-MA-lCS PROB O LSl-BCC-MA-104 PROB O LSl-BCC-MA-105 PROB O L51-BCC-MA-1E4 PROB O L51-BCC-MA-1ES PROB O L51-BCC-MA-1G4 PROB 7.60340632603406E-05 LSl-BCC-MA-lGS PROB 0.000114051094890511 L51-BCC-MA-1K4 PROB 0.00163853406326034 LSl-BCC-MA-lKS PROB 0.000912408759124088 L51-BCC-MA-1L4 PROB 0.000893400243309002 L51-BCC-MA-1L5 PROB 0.000456204379562044 L51-BCC-MA-2G4 PROB 7.60340632603406E-05 L51-BCC-MA-2GS PROB 0.000133059610705596

ENTGGGX083-RPT-001 Data Sensitivity Study Page 91 of 132 L62-INV-MA-1Y80 PROB 0.000969529085872576 L62~1NV-MA-1Y82 PROB 0.000969529085872576 L62-INV-MA-1Y87 PROB 0.000969529085872576 L62-INV-MA-1Y88 PROB 0.000969529085872576 L62-INV-MA-1Y95 PROB 0.000969529085872576 L62-INV-MA-1Y96 PROB 0.000969529085872576 L62-INV-MA-1Y99 PROB 0.000969529085872576 N19-FLT-MA-CFFFA PROB 0.000745791604517366 N19-FLT-MA-CFFFB PROB 0.000745791604517366 N19-FLT-MA-CFFFC PROB 0.000745791604517366 N19-FLT-MA-CFFFD PROB 0.000745791604517366 N19-FLT-MA-TRNA PROB 0.000745791604517366 N19-FLT-MA-TRNB PROB 0.000745791604517366 N19-FLT-MA-TRNC PROB 0.000745791604517366 N19-FLT-MA-TRND PROB 0.000745791604517366 N19-FLT-MA-TRNE PROB 0.000745791604517366 N19-FLT-MA-TRNF PROB 0.000745791604517366 N19-FLT-MA-TRNG PROB 0.000745791604517366 N19-FLT-MA-TRNH PROB 0.000745791604517366 N19-HTX-MA-B001A PROB 0.000980183251651396 N19-HTX-MA-B001B PROB 0.000340933304922225 N19-HTX-MA-B001C PROB 0.00021308331557639 N19-HTX-MA-B002A PROB 0.000980183251651396 N19-HTX-MA-B002B PROB 0.000340933304922225 N19-HTX-MA-B002C PROB 0.00021308331557639 N19-HTX-MA-B003A PROB 0.000980183251651396 N19-HTX-MA-B003B PROB 0.000340933304922225 N19-HTX-MA-B003C PROB 0.00021308331557639 N19-HTX-MA-B004A PROB 0.000980183251651396 N19-HTX-MA-B004B PROB 0.000340933304922225 N19-HTX-MA-B004C PROB 0.00021308331557639 N19-MDP-MA-C002A PROB 0.000980183251651396 N19-MDP-MA-C002B PROB 0.000340933304922225 N19-MDP-MA-C002C PROB 0.00021308331557639 N19-MDP-MA-C003A PROB 0.000070956744086938 N19-MDP-MA-C003B PROB 0.000070956744086938 N19-MDP-MA-C003C PROB 0.000070956744086938 P41-CTS-MA-C003A PROB 0.00501939310974219 P41-CTS-MA-C003B PROB 0.00501939310974219 P41-CTS-MA-C003C PROB 0.00501939310974219 P41-CTS-MA-C003D PROB 0.00501939310974219 P41-TRN-MA-SSW_A PROB 0.00282958463254493 P41-TRN-MA-SSW_B PROB 0.00296752604760818 P41-TRN-MA-SSW_C PROB 0.0055446178491257

ENTGGGX083-RPT-001 Data Sensitivity Study Page 92 of 132 P42-HTX-MA-B001A PROB 0.000285127737226277 P42-HTX-MA-B001B PROB 0.000323144768856448 P42-HTX-MA-B001C PROB 0.000285127737226277 P42-MDP-MA-C001A PROB 0.000285127737226277 P42-MDP-MA-C001B PROB 0.000323144768856448 P42-MDP-MA-C001C PROB 0.000285127737226277 P43-HTX-MA-B001A PROB 0.012103132324739 P43-HTX-MA-B001B PROB 0.0104197741316855 P43-HTX-MA-B001C PROB 0.0118474323460473 P43-MDP-MA-C001A PROB 0.0008736415938632

P43-MDP-MA-C001B PROB 0.00121457489878542 P43-MDP-MA-C001C PROB 0.00196036650330279 P47-MCS-MA-C002A PROB 0.324 P47-MCS-MA-C002B PROB 0.0137 P47-MCS-MA-C002C PROB 0.00174 P47-MCS-MA-C002D PROB 0.00389 P47-MCS-MA-C002E PR,PB 0.00114 P47-MCS-MA-C002F PROB 0.000609 P47-MCS-MA-C002J PROB 0.289 P47-MCS-MA-C002K PROB 0.00262 P47-MDP-MA-C001A PROB 0.0698 P47-MDP-MA-COOiB PROB 0.00389 P47-MDP-MA-C001C PROB 0.00143 P47-MDP-MA-C001D PROB 0.00562 P47-MDP-MA-C001E PROB 0.000148 P47-MDP-MA-C001F PROB 0.0000745 P47-MDP-MA-C001J PROB 0.00475 P47-MDP-MA-C001K PROB 0.0171 P47-MDP-MA-C001L PROB 0.000259 P47-MDP-MA-C001M PROB O P47-WEL-MA-WELL1 PROB 1 P47-WEL-MA-WELL3 PROB 0.149996198296837 P47-WEL-MA-WELL4 PROB O P47-WEL-MA-WELL5 PROB 0.149996198296837 P47-WEL-MA-WELL6 PROB O P51-DRY-MA-DRYA PROB 0.00889830025096965 PSl-DRY-MA-DRYB PROB 0.00838806658301012 PSl-MDC-MA-COOlA PROB 0.0148586274448479 PSl-MDC-MA-COOlB PROB 0.00894078627501713 PSl-MDC-MA-COOlC PROB 0.0238424012610703 P64-AOV-MA-TR1 PROB O P64-AOV-MA-TR2 PROB O P64-ENG-MA-TRNA PROB 0.00608752566735113 P64-ENG-MA-TRNB PROB 0.00723771769716328

ENTGGGX083-RPT-001 Data Sensitivity Study Page 93 of 132 P64-MDP-MA-C002N PROB 0.00324910639592365 P64-Mov.:MA-FA10A PROB O P64-MOV-MA-FA10B PROB O P71-CHR-MA-B001A PROB 0.037662522810219 P71-CHR-MA-B001B PROB 0.372833599452555 P71-CHR-MA-B001C PROB 0.28794099756691 P75-DGN.:.MA-DG11 PROB 0.0146461169417193 P'75-DGN-MA-DG12 PROB 0.0160983344741045 P81-DGN-MA-DG13 PROB 0.0141215764154487 R27-BAC-MA-EAST PROB O R27-BAC-MA-WEST PROB O R27-TAC-MA-BAXWL PROB S.57899939172749E-05 R27-TAC-MA-FRANK PROB 0.00439096715328467 R27-TAC-MA-PORTG PROB 0.000123555352798054 TSl-CLU-MA-BOOlA PROB 0.000189558141303521 T51-CLU-MA-B002A PROB 0.000509544452049585 T51-CLU-MA-B003A PROB 0.000456204379562044 T51-CLU-MA-B004B PROB 0.000456204379562044 TSl-CLU-MA-BOOSB PROB 0.000456204379562044 T51-CLU-MA-B006A PROB 0.000456204379562044 T51-CLU-MA-B007 A PROB 0.000456204379562044 T51-CLU-MA-B007B PROB 0.000456204379562044 X77-DGN-MA-DG1RM PROB 0.000152578142824549 X77-DGN-MA-DG2RM PROB 3.65997414252034E-05 X77-DGN-MA-DG3Ro/' PROB 0.000229104874895429 Y47-FNS-MA-C01AA PROB 0.000860901969731538 Y47-FNS-MA-C01AB PROB 0.0016067444926097 Y47-FNS-MA-C01BB PROB 0.00157744458491 Z77-TRN-MA-SSBRA PROB 0.00315294251824818 277-TRN-MA-SSBRB PROB 0.0178267563868613

ENTGGGX083-RPT-001 Data Sensitivity Study Page 94 of 132 Appendix E- CR Functional Failure Review (September 1, 2012 -August 31, 2018)

ENTGGGX083-RPT-001 Data Sens_itivity Study Page 95 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description (if applicable)

CR-GGN- 1B21F002 20-Feb-16 Component not modeled in PRA or No impact 2016-1065 EOOS on reliability CR-GGN- 1821F113 15-Jan-13 Component not modeled in PRA or No impact 2013-00332 EOOS - -,

on reliability CR-GGN- 1B21HF103A 2-Mar-14 Component not modeled in PRA or No impact 2014-2264 EOOS on reliability CR-GGN- 1833D003A 30-0ct-13 Component not modeled in PRA or No impact 2013-06764 EOOS on reliability CR-GGN- 1B33K143A 5-0ct-15 Component not modeled in PRA or No impact 2015-05760 EOOS on reliability CR-GGN- 1C41F0048 22-Aug-15 C41-EPV-CC-F004B NORMALLY CLOSED EXPLOSIVE EPVCC 2015-4832 VALVE C41-F004B FAILS TO OPEN CR-GGN- lC51K601A 5-Jan-13 System not modeled in PRA or EOOS No impact 2013-00085 on reliability CR-GGN- 1C61N001B 4-Nov-14 Component not modeled in PRA or No impact 2014-7495 EOOS on reliability CR-GGN- 1C61R001A 5-Jun-14 Component not modeled in PRA or No impact 2014-04511 EOOS on reliability

~

CR-GGN- 1C71N652D 31-Jan-13 Component not modeled in PRA or No impact 2013-00757 EOOS on reliability CR-GGN- 1C71N652D 7-Feb-13 Component not modeled in PRA or No impact 2013-00965 EOOS on reliability CR-GGN- 1D17P024/26 2-Feb-15 System not modeled in PRA or EOOS No impact 2015-638 on reliability

ENTGGGX083-RPT-001 Data Sensitivity Study Page 96 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description {if applicable)

CR-GGN- 1E21AK108 21-Feb-14 Component not modeled in PRA or No impact 2014-01696 EOOS on reliability CR-GGN- 152-1705 9-Feb-14 E22-CBR-00-1705 NORMALLY OPEN CIRCUIT BREAKER CBROO 2014-873 152-1705 FAILS TO CLOSE CR-GGN- 1E30N003B/D 8-Mar-15 E30-ASL-DN-N003B SUPP POOL LEVEL SENS/TRANS E30- ASLDN 2015-1429 LT-N003B FAILS TO FUNCTION CR-GGN- 1E30N003B/D 8-Mar-15 E30-ASL-DN-N003D SUPP POOL LEVEL SENS/TRANS E30- ASLDN 2015-1429 LT-N003D FAILS TO FUNCTION CR-GGN- 1E51F063 17-Dec-13 ES l-MOV-OC-F063 NORMALLY OPEN MOTOR DRIVEN MOVOC 2013-07720 VALVE E51F063 FAILS CLOSED CR-GGN- 1E51F064 12-Mar-15 ES l-MOV-OC-F064 NORMALLY OPEN MOTOR DRIVEN MOVOC 2015-1532 VALVE E51F064 FAILS CLOSED CR-GGN- 1E51F064 20-Mar-15 E51-MOV-OC-F064 NORMALLY OPEN MOTOR D~IVEN MOVOC 2015-1677 VALVE E51F064 FAILS CLOSED CR-GGN- 1E51K603 9-Jan-14 E51-TDS-FS-C001-R RCIC TURBINE-DRIVEN PUMP FAILS TDS FS 2014-00146 TO START CR-GGN- 1E51K603 18-Nov-14 E51-TDS-FS-C001-R RCIC TURBINE-DRIVEN PUMP FAILS TDS-FS 2014-7810 TO START CR-GGN- 1E61J002B 8-May-13 E61-ASP-DN-J002B TRAIN B CNTMNT HYDROGEN ASP DN 2013-03132 ANALYZER FAILS TO FUNCTION CR-GGN- 1G33C001A/B 2-0ct-14 Component not modeled in PRA or No impact 2014-6799 EOOS on reliability CR-GGN- 1G33C001A/B 26-Mar-15 Component not modeled in PRA or No impact 2015-1823 EOOS on reliability CR-GGN- 1G33C001A/B 31-Jan-16 Component not modeled in PRA or No impact 2016-607 EOOS on reliability

ENTGGGX083-RPT-001 Data Sensitivity Study Page 97 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description {if applicable)

CR-GGN- \ 1G33F033 31-Jul-13 Component not modeled in PRA or No impact 2013-4963 EOOS on reliability CR-GGN- 1G33K600 28-Apr-13 Component not modeled in PRA or No impact 2013-02899 EOOS on reliability CR-GGN- 1M41F008 28-Aug-15 Component not modeled in PRA or I No impact 2015-4977 EOOS on reliability CR-GGN- 1M71F592A 9-Jun-14 System not modeled in PRA, No impact 2014-4594 component not modeled in EOOS on reliability CR-GGN- 1821F019 3-Mar-16 Component not modeled in PRA or No impact 2016-1760 EOOS on reliability CR-GGN- 1B21F032A 21-Feb-14 B21-CKV-OO-F032A NORMALLY OPEN CHECK VALVE CKVOO 2014-01667 B21-F032A FAILS TO CLOSE CR-GGN- 1B21F032B 24-Feb-16 B21-CKV-OO-F032B NORMALLY OPEN CHECK VALVE CKVOO 2016-1308 B21-F032B FAILS TO CLOSE CR-GGN- 1E51F040 29-Jan-13 ES 1-CKV-CC-F040 RCIC TURBINE EXHAUST LINE CHECK CKVOO 2013-00689 VALVE F040 FAILS TO OPEN CR-GGN- 1P52F122 24-Jun-15 System not modeled in PRA or EOOS No impact 2015-3676 on reliability CR-GGN- 1P71F149 20-Feb-14 Component not modeled in PRA or No impact 2014-01597 EOOS on reliability CR-GGN- Nll pipe 17-Mar-14 Pipe failure not included in PRA data No impact 2014-2824 on reliability CR-GGN- 1N21C001B 20-Nov-12 N21-TDP-FR-C001B-F MAIN FEEDWATER TURBINE TDP FR 2012-12487 DRIVEN PUMP N21-C001B FAILS TO RUN CR-GGN- 1N30N011B . 30-Jul-13 System not modeled in PRA or EOOS No impact 2013-04943 on reliability

ENTGGGX083-RPT-001 Data Sensitivity Study Page 98 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description (if applicable)

CR-GGN- 1N32D038 9-0ct-13 Component not modeled in PRA or No impact 2013-6384 EOOS on reliability CR-GGN- 1N41M701A 29-Dec-12 System not modeled in PRA or EOOS No impact 2012-13290 on reliability CR-GGN- 1N41M701A 5-Jan-13 System not modeled in PRA or EOOS No impact 2013-00083 on reliability CR-GGN- 1N41M705 14-Jan-13 System not modeled in PRA or EOOS No impact 2013-00319 on reliability CR-GGN- 1N41M791 29-Mar-14 System not modeled in PRA or EOOS No impact 2014-3131 on_ reliability CR-GGN- NSl TVR 26-Mar-14 System not modeled in PRA or EOOS No impact 2014-3043 on reliability CR-GGN- 1N71C001A 21-Nov-13 N71-MDP-FR-C001A MOTOR DRIVEN PUMP N71-C001A MDP FR 2013-07211 FAILS TO RUN CR-GGN- 1P41R700A 5-Jan-14 Component not modeled in PRA or No impact 2014-0051 EOOS on reliability CR-GGN- 52-170124 4-Dec-13 P41-MDS-Fl-C002C-S STANDBY MOTOR DRIVEN PUMP MDS-Fl 2013-7426 P41-C002 FAILS TO RUN IN FIRST HOUR -

CR-GGN- SP41F074A 14-Dec-13 Component not modeled in PRA or No impact 2013-07656 EOOS on reliability GGCR-2012- lPSlCOOlA 25-Sep-12 PSl-MDC-FR-COOlA-P PS PLANT AIR COMPRESSOR COOlA MDC FR 11043 FAILS TO CONTINUE RUNNING CR-GGN- 1P51C001A 8-Aug-13 PSl-MDC-FR-COOlA-P PS PLANT AIR COMPRESSOR COOlA MDC FR 2013-5153 FAILS TO CONTINUE RUNNING CR-GGN- 1P51C001A 15-0ct-13 P51-MDC-FR-C001A-P PS PLANT AIR COMPRESSOR COOlA MDC FR 2013-06508 FAILS TO CONTINUE RUNNING

ENTGGGX083-RPT-001 Data Sensitivity Study Page 99 of 132 PRA Data Condition Component Event'Date PRA Impact Report Associated BE or Disposition BE Description {if applicable)

CR-GGN- 1P51C001A 13-Nov-13 P51-MDC-FR-C001A-P PS PLANT AIR COMPRESSOR COOlA MDC FR 2013-7038 '~ FAILS TO CONTINUE RUNNING CR-GGN- 1P51C001A 26-Aug-14 P51-MDC-FR-C001A-P PS PLANT AIR COMPRESSOR COOlA MDC FR 2014-6114 FAILS TO CONTINUE RUNNING CR-GGN- 1P51C001A 16-Mar-15 P51-M DC-FR-C001A-P PS PLANT AIR COMPRESSOR C001A MDC FR 2015-1582 FAILS TO CONTINUE RUNNING CR-GGN- 1P51C001B 23-May-14 P51-MDC-FR-C001B-P AIR COMPRESSOR C001B FAILS TO MDCFS 2014-4274 START

-GGCR-2012- 1P51C001C 23-Sep-12 P51-MDC-FR-C001C-P PS PLANT AIR COMPRESSOR COOlC MDC FR 10982 FAILS TO CONTINUE RUNNING CR-GGN- 1P51C001C 11-Aug-13 P51-MDC-FR-C001C-P PS PLANT AIR COMPRESSOR C001C MDC FR 2013-5209 FAILS TO CONTINUE RUNNING CR-GGN- 1P51C001C 10-Aug-15 P51-MDC-FR-C001C-P AIR COMPRESSOR C001C FAILS TO MDCFS 2015-4584 START CR-GGN- 1P75E001A 17-Sep-13 P75-DGN-Fl-DG11 DG11 FAILS TO RUN DURING 1ST DGN Fl 2013-05899 HOUR OF OPERATION CR-GGN- 1P75E001A 21-Nov-15 P75-DGN-F1-DG11 DG11 FAILS TO RUN DURING lST DGN Fl 2015-6831 HOUR OF OPERATION CR-GGN- 1P75E001B 21-May-13 P75-DGN-F1-DG12 DG12 FAILS TO RUN DURING lST DGN Fl 2013-03423 HOUR OF OPERATION CR-GGN- 1P75R608B 13-Nov-13 Component not modeled in PRA - , No impact 2013-07040 failure would not prevent DG 12 from on reliability continued operation CR-GGN- DG12-151GD 19-Nov-14 P75-DG N-FS-DG 12 DG12 FAILS TO START DGN FS 2014-7826 CR-GGN- 1P81N606 13-Jul-15

Component not modeled in PRA or No impact 2015-03985 EOOS - on reliability

ENTGGGX083-RPT-001 Data Sensitivity Study Page 100 of 132 PRA-Data Condition Component Event Date

PRA Impact

_ Report Associated BE or Disposition BE Description (if applicable)

CR-GGN- 1R14S001A 12-Jul-13 System not modeled in PRA or EOOS No impact 2013-4553 - on reliability CR-GGN- 1R14S001A 3-0ct-13 System not modeled in PRA or EOOS No impact 2013-6263 on reliability CR-GGN- 1R14S001A 27-Apr-14 System not modeled in PRA or EOOS No impact 2014-3733 on reliability CR-GGN- 1R14S001B , 7-Feb-15 System not modeled in PRA or EOOS No impact 2015-0801 on reliability GGCR-2012- AUX BLDG 5-0ct-12 System not modeled in PRA or EOOS No impact 11352 on reliability CR-GGN- Aux Bldg Penet 24-Apr-13 System not modeled in PRA or EOOS No impact 2013-02812 on reliability CR-GGN- no 11-Feb-13 System not modeled in PRA or EOOS No impact 2013-01104 on reliability CR-GGN- no AUX BLDG 5-Nov-12 System not modeled in PRA or EOOS No impact 2012-12152 on reliability CR-GGN- no Aux Building 2-Aug-15 System not modeled in PRA or EOOS No impact 2015-4423 on reliability CR-GGN- no Auxiliary 17-Jun-14 System not modeled in PRA or EOOS No impact 2014-4733 Building on reliability CR-GGN- no Roof 30-Nov-13 System not modeled in PRA or EOOS No impact 2013-7345 on reliability CR-GGN- T48 SBGT System 1-0ct-15 System not modeled in PRA or EOOS No impact 2015-5661 on reliability CR-GGN- 1T46B002A 17-Jul-14 System not modeled in PRA or EOOS No impact 2014-05306 on reliability

ENTGGGX083-RPT-001 Data Sensitivity Study Page 101 of 132 PRA Data Condition Component Event Date PRA*lmpact Report Associated BE or Disposition BE Description (if applicable)

CR-GGN- 1T4680048 26-Aug-14 System not mode_led in PRA or EOOS No impact 2014-06116 on reliability CR-GGN- 1T4680058 2-May-15 System not modeled in PRA or EOOS No impact 2015-02614 on reliability CR-GGN- 52-154145 1-Apr-15 System not modeled in P~A or EOOS Also breaker not mapped in EOOS No impact 2015-01938 on reliability CR-GGN- 52-151130 15-Mar-16 Component not modeled in PRA or No impact 2016-2386 EOOS on reliability CR-GGN- X70 Roof 21-0ct-13 System not modeled in PRA or EOOS No impact 2013-6597 on reliability CR-GGN- X70 Roof 20-Dec-13 System not modeled in PRA or EOOS No impact 2013-7802 on reliability CR-GGN- 1Y47F002 8-Dec-14 Y47-MOD-CC-F02AA MOD 1Y47-F002A FAILS TO OPEN MOD CC 2014-8155 CR-GGN- 1Y47-F002A 18-Jan-15 Y47-MOD-CC-F02AA MOD 1Y47-F002A FAILS TO OPEN MOD CC 2015-0342 CR-GGN- 1Y47F002B/N004B 5-Feb-15 Y47-MOD-CC-F02BB MOD 1Y47-F0028 FAILS TO OPEN MOD CC 2015-00745 CR-GGN- 1Y47Y001A 29-Apr-13 Y47-MOD-CC-F02BB MOD 1Y47-F002B FAILS TO OPEN MOD CC 2013-02932 CR-GGN- Various 27-Dec-14 Y47-MOD-CC-F02AA MOD 1Y47-F002A FAILS TO OPEN MOD CC 2014-08441 CR-GGN- SZ51B002B 31-0ct-14 System not modeled in PRA or EOOS No impact 2014-7413 on reliability CR-GGN- SZ518002B 24-Mar-15 System not modeled in PRA or EOOS No impact 2015-1728 on reliability

ENTGGGX083-RPT-001 Data Sensitivity Study Page 102 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description (if applicable)

CR-GGN- SZ51B002B 6-Apr-15 System not modeled in PRA or EOOS No impact 2015-2037 on reliability CR-GGN- 1Z778001A 1-Apr-15 Z77-FNS-FR-B001A-S UNIT 1 TRAIN A SUPPLY SIDE FAN FNS FR 2015-01927 1Z77-8001A FAILS TO RUN CR-GGN- 2Z77C001A 17-Jul-14 Z77-FNS-Fl-2C01A-S UNIT 2 TRAIN A EXHAUST SIDE FAN FNS FR 2014-05317 2277-COOlA FAILS TO RUN CR-GGN- 52-164101 3-0ct-13 Component not modeled in PRA or No impact 2013-6274 EOOS on reliability CR-GGN- 1N41M703 (XFM R 29-Mar-16 Component not modeled in PRA or No impact 2016-2950 Diff Phase B} EOOS on reli.ability CR-GGN- 1C71N0018, 29-Mar-16 Component not modeled in PRA or No impact 2016-2950 1C71N0019 (TCV EOOS on reliability Fast Closure Chs

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B&C)

CR-GGN- 1E31N684A 1-Apr-16 Component not modeled in PRA or No impact 2016-3063 EOOS on reliability CR-GGN- 1-Apr-16 Component not modeled in PRA or No impact 2016-3063 EOOS on reliability CR-GGN- 1833N150B 2-Apr-16 Component not modeled in PRA or No impact 2016-3079 EOOS on reliability CR-GGN- 1B33F060B(RX 2-Apr-16 Component not modeled in PRA or No impact 2016-3079 Recirc Loop B FCV) EOOS on reliability CR-GGN- lCllAOOlBM 11-Apr-16 Component not modeled in PRA or No impact 2016-3238 EOOS on reliability CR-GGN- 1P60F009 22-Apr-16 Component not modeled in PRA or No impact 2016-3551 EOOS on reliability

ENTGGGX083-RPT-001 Data Sensitivity Study Page 103 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description {if applicable)

CR-GGN- 1G36AF002 22-May-16 Component not modeled in PRA or No impact 2016-4192 EOOS on reliability CR-GGN- 1P75L605B (D2 2-Jun-16 P75-DGN-FS-DG12 DG12 FAILS TO START DGN FS 2016-04410 EDG Lockout Relay) 1P75E001B (D2EDG)

CR-GGN- 1N32F515C (Main 17-Jun-16 Component not modeled in PRA or No impact 2016-4766 Stop Valve) EOOS on reliability CR-GGN- 1N31D001 25-Jun-16 Component not modeled in PRA or No impact 2016-4998 EOOS on reliability CR-GGN- 1E12F0188 29-Jun-16 External valve leak not modeled No impact 2016-5087 on reliability CR-GGN- 2RJ5S121 (Service 30-Jun-16 R15-PTR-LP-SVC21 SERVICE TRANSFORMER 21 PTR LP 2016-5153 XFMR #21) HARDWARE FAILURE 2R11S123 (BOP XFMR #23)

CR-GGN- 1Y47F001A 3-Jul-16 Y47-MOD-CC-F01AA MOD 1Y47-F001A FAILS TO OPEN MOD CC 2016-05211 CR-GGN- 152-1705 8-Jul-16 E22-CBR-CC-1704 NORMALLY CLOSED CIRCUIT CBR CC 2016-5329 BREAKER 152-1704 FAILS TO OPEN CR-GGN- 1E12F048A 4-Sep-16 No FF, valve was just out of spec., No impact 2016-6798 and needed throttling adj. on reliability CR-GGN- 1B21F002 9-Sep-16 Component not modeled in PRA or No impact 2016-6887 EOOS on reliability CR-GGN- 1G36F101 13-Sep-16 Component not modeled in PRA or No impact 2016-06999 EOOS on reliability

ENTGGGX083-RPT-001 Data Sensitivity Study Page 104 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description (if applicable)

CR-GGN- 1E22C003(HPCS 27-Jan-17 Component not modeled in PRA or No impact 2017-916 Jockey Pump) EOOS on reliability CR-GGN- 1N19C002B 10-Feb-17 N19-MDP-FR-C002B CONDENSATE BOOSTER MOTOR MDP FR 2017-1486 DRIVEN PUMP N19-C002B FAILS TO RUN CR-GGN- 1B21CKOOSA 23-Feb-17 821-TIM-DD-KSA DIVISION 1 (A) 105 SEC TIMER 821- TIMDO 2017-1939 KSA FAILS CR-GGN- 1Nl9C002C 24-Feb-17 N19-MOP-FR-C002C CONDENSATE BOOSTER MOTOR MOP FR 2017-1956 DRIVEN PUMP N19-C002C FAILS TO RUN CR-GGN- 1T48R600A (SGTS 24-Mar-17 Component not modeled in PRA or No impact 2017-2968 Filter train A Flow EOOS on reliability Recorder)

CR-GGN- 1P51F256A (Dryer 26-Mar-17 No PRA event to map spurious open AOVOC 2017-3025 A Left Tower to. Assume valve is AOV Purge Flow Valve)

CR-GGN- 1P41N016A ( SSW 28-Mar-17 Component not modeled in PRA or No impact 2017-3084 Loop A Discharge EOOS on reliability Flow Xmittter)

CR-GGN- 1N37F100A 4-Apr-17 Component not modeled in PRA or No impact 2017-3333 (Water Injection EOOS on reliability Valve)

CR-GGN- 1T48R602B 7-Apr-17 Component not modeled in PRA or No impact 2017-3481 (Enclosure EOOS on reliability Building Outside DP Recorder) '

I

ENTG GGX083-RPT-001 Data Sensitivity Study Page 105 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description (if applicable)

CR-GGN- 1B21KOOSA 26-May-17 821-TIM-DD-KSA DIVISION 1 (A) 105 SEC TIMER 821- TIMDD 2017-5374 K5A FAILS CR-GGN- 1P51C0018 13-Jun-17 PSl-MDC-FR-COOlB-P PS PLANT AIR COMPRESSOR COOlB MDC FR 2017-5917 FAILS TO CONTINUE RUNNING CR-GGN- Door OC 516 10-Jul-17 Component not modeled in PRA or No impact 2017-6705 EOOS on reliability CR-GGN- 1N21A001B 13-Jul-17 Component not modeled in PRA or No impact 2017-06842 (Control Fluid EOOS on reliability Reservoir) 1N21F5198 (RFPT B CV Positioner7 Assembly)

CR-GGN- 1T48F005 (Stm 14-Jul-17 Component not modeled in PRA or No impact 2017-6881 Tunnel SGTS Flow EOOS on reliability Control Valve)

CR-GGN- 1Y47F003B 4-Aug-17 Y47-MOD-CC-F01BB MOD 1Y47-F001B FAILS TO OPEN MOD CC 2017-07635 (1Y47C001B Inlet Damper)

CR-GGN- 1E12C002A, 27-Aug-17 E12-MDS-FR-C002A MOTOR-DRIVEN PUMP C002A FAILS MDSFR 2017-8434 1E12F006A TO CONTINUE RUNNING CR-GGN- 1C61R001A (SSW 28-Aug-17 Component not modeled in PRA or No impact 2017-8489 A System Flow EOOS on reliability (RSM) indicator)

CR-GGN- 1M23Y002N (208' 7-Sep-17 Component not modeled in PRA or No impact 2017-08848 Airlock Outer EOOS on reliability Door)

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ENTGGGX083-RPT-001 Data Sensitivity Study Page 106 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description {if applicable)

CR-GGN- 1E22S001 {HPCS 12-Sep-17 L11-BAT-LP-1C3 DIV Ill BATIERY 1C3 FAILS (NO BAT LP 2017-9058 DG) OUTPUT/POWER)

CR-GGN- 1017P024 {SGTR B 5-0ct-17 Component not modeled in PRA or No impact 2017-10042 Vent Normal EOOS on reliability Range Panel),

1C91K106 -

(Horizon Supervisory Sys)

CR-GGN- 1E61F003B 26-0ct-17 E61-MOV-OO-F003B NORMALLY OPEN MOTOR DRIVEN MOVOO 2017-10756 (Drywell Purge VALVE F003B FAILS TO CLOSE Supply)

CR-GGN- 1P60F009 (SPCU 27-0ct-17 Component not modeled in PRA or No impact 2017-10797 Return from CNDS EOOS on reliability PC Filters)

CR-GGN- 1833C001B(Rx 15-Nov-17 No PRA failure, only fail to trip is No impact 11427 Recirculation relevant to PR-A on reliability pump B)

CR-GNN~ 1C11A001FH 25-Nov-17 Component not modeled in PRA or No impact 2017-11739 (Accumulator for EOOS on reliability HCU 24-33)

CR-GGN- 1P60F009 (SPCU 27-Nov-17 Component not modeled in PRA or No impact 2017-11786 Return from CNDS EOOS on reliability PC Filters)

CR-GGN- 1E31AK002A & B 12-Dec-17 Component not modeled in PRA or No impact 2017-12314 (Agastat Relays EOOS on reliability Skeletal Entry)

ENTGGGX083-RPT-001 Data Sensitivity Study Page 107 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description (if applicable)

CR-GGN- lESlCOOl (RCIC 12-Dec-17 E22-CBR-CO-l 704 BREAKER 152-1704 FAILS OPEN CBR CO 2017-12299 Pump), 152-1704 (ESF Trans #12 Source Bus 17 AC)

CR-GGN- 1P41N018B (SSW 7-Jan-18 Component not modeled in PRA or No impact 2018-00200 Clg Tower B EOOS on reliability Return Flow Xmitter)

CR-GGN- 1N11F037A, 8-Jan-18 Component not modeled in PRA or No impact 2018-00218 1N11F039A, EOOS on reliability 1N33F080A & B, 1N33F178 CR-GNN- lCllAOOlHP 10-Jan-18 Component not modeled in PRA or No impact 2018-00303 (Accumulator for EOOS on reliability HCU 32-57)

CR-GGN- 1C91K010P(P 20-Jan-18 Component not modeled in PRA or No impact 2018-564 MUX VME Chassis) EOOS on reliability

- CR-GGN- SDl 7L654 (SBGT 22-Jan-18 Component not modeled in PRA or No impact 2018-591 A/B Hi Rad/ EFFFL EOOS on reliability Rad Mon)

CR-GGN- 1017N205E (SGTS 23-Jan-18 Component not modeled in PRA or No impact 2018-643 B Vent Stack Flow EOOS on reliability Rate)

CR-GGN- SD17L660 (EFFL 24-Jan-18 Component not modeled in PRA or No impact 2018-717 Rad Mon Trouble) EOOS on reliability CR-GGN- 1H13P825JC05 30-Jan-18 Component not modeled in PRA or No impact 2018-00918 EOOS on reliability

ENTGGGX083~RPT-001 Data Sensitivity Study Page 108 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description (if applicable)

CR-GGN- SD17L654(SBGT 12-Feb-18 Component not modeled in PRA or No impact 2018-1307 A/B Hi Rad/ EFFFL EOOS on reliability Rad Mon)

CR-GGN- 1P818003B(HPCS 17-Feb-18 Component not modeled in PRA or No impact 2018-01512 DG Jacket Water EOOS on reliability Heater),

1P81N044B (Engine B JW Heater Temp Sw)

CR-GGN- 525180028 21-Feb-18 Component not modeled in PRA or No impact 2018-1629 (Control Room AC) EOOS on reliability CR-GGN- 1D17P025 (SGTS B 24-Feb-18 Component not modeled in PRA or No impact 2018-1764 Vent Noble Gas EOOS on reliability Monitor)

CR-GGN- 1017P027 (SGTS A 24-Feb-18 Component not modeled in PRA or No imp~ct 2018-1767 Vent Noble Gas EOOS on reliability Pallet)

CR-GGN- 1D17P025 15-Mar-18 Component not modeled in PRA or No impact 2018-2410 EOOS on reliability CR-GGN- 1Tl01A319A 31-Mar-18 Component not modeled in PRA or No impact 2018-2962 (Outer Aux. EOOS on reliability Railroad Bay Door)

CR-GGN- SGTS A/B SPI NG 6-Apr-18 Component not modeled in PRA or No impact 2018-3222 EOOS on reliability

CR-GGN- 1D17P025 (SGTS B 7-May-18 Component not modeled in PRA or No impact 2018-05198 Vent Noble Gas EOOS on reliability Monitor)

ENTGGGX083-RPT-001 Data Sensitivity Study Page 109 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description {if applicable)

CR-GGN- 1D17J115 21-May-18 Component not modeled in PRA or No impact 2018-05889 EOOS on reliability CR-GGN- 525180028 3-Jun-18 Component not modefed in PRA or No impact 2018-06469 (Control Room AC) EOOS on reliability CR-GGN- 1C61R025 26-Jun-18 Component not modeled in PRA or No impact 2018-7431 (Remote SD Sys EOOS on reliability Transf Panel Relay)

CR-GGN- 15_2-1702 (HPCS 5-Jul-18 E22-MDS-FS-C001 HPCS MOTOR DRIVEN PUMP COOl MOS FS 2018-7762 Pump 1E22C001) FAILS TO START CR-GGN- 1T48K699B (SGTS 12-Jul-18 Component not modeled in PRA or No impact 2018-8005 Instrument Power EOOS on reliability Supply) (

CR-GGN- 1833C001A (Rx 30-Jul-18 No PRA failure, only fail to trip is No impact 2018-8706 Recirc Pump A relevant to PRA on reliability Motor)

CR-GGN- Dl 7L024 (SGTS B 4-Aug-18 Component not modeled in PRA or No impact 2018-8958 EFFL Rad Mon EOOS on reliability Trouble) -0 CR-GGN- 1P41N018B (SSW 10-Aug-18 Component not modeled in PRA or No impact 2018-9242 ClgTower B EOOS on reliability Return Flow Xmitter)

CR-GGN- SD17L654(SBGT 13-Aug-18 Component not modeled in PRA or No impact 2018-9330 A/B Hi Rad/ EFFFL EOOS on reliability Rad Mon)

ENTGGGX083-RPT-001 Data Sensitivity Study Page 110 of 132 PRA Data Condition Component Event Date PRA Impact Report Associated BE or Disposition BE Description {if applicable)

CR-GGN- 1D17N127 (Ctmt 16-Aug-18 Component not modeled in PRA or No impact 2018-9436 Vent Axm NGP HR EOOS on reliability NG Rad Detect.)

eR-GGN- 1N23F514B (FW 21-Aug-18 Component not modeled in PRA or No impact 2018- HTR 68 Drn Valve) EOOS on reliability 9632/9635 CR-GGN- 1E12F048A RHR 23-Aug-18 E12-MOV-OC-F048A MOTOR-OPERATED VALVE F048A MOVOC 2018-9705 Hx A Bypass Valve) PLUGS

ENTGGGX083-RPT-001 Data Sensitivity Study Page 111 of 132 Appendix F - GGNS Functional Failures (September 1, 2006 -August 31, 2018)

ENTGGGX083-RPT-001 Data Sensitivity Study Page 112 of 132 Type Code Description Component Plant Documentation AOVCC Normally Closed Air Operated Valve F034 Fails to Open M41-AOV-CC-F034 CR-GGN-2012-09747 AOVOC Air-Operated Valve Fails to Remain Open 1P51F256A CR-GGN-2017-3025 AOVOC Normally Open Air Operated Valve F289 Fails Closed P43-AOV-OC-VF289 CR-GGN-2009-04 781 AOVOC Air-Operated Valve F011 Fails to Remain Open Due to Hardware Failure P44-AOV-OC-F011 CR-GGN-2007-05463 ASLDN SUPP POOL LEVEL SENS/TRANS E30-LT-N003B FAILS,TO FUNCTION E30-ASL-D N-N003 B CR-GGN-2015-1429 ASLDN SUPP POOL LEVEL SENS/TRANS E30-LT-N003D FAILS TO FUNCTION E30-ASL-DN-N003D CR-GGN-2015-1429 ASP DN TRAIN B CNTMNT HYDROGEN ANALYZER FAILS TO FUNCTION E61-ASP-DN-J002B CR-GGN-2013-03132 BAT LP DIV Ill BATTERY 1C3 FAILS (NO OUTPUT/POWER) L11-BAT-LP-1C3 CR-GGN-2017-9058

CBR CC Circuit Breaker Failure 1EQ18AG CR-GGN-2011-08539 CBR CC NORMALLY CLOSED CIRCUIT BREAKER 152-1704 FAILS TO OPEN E22-CB R-CC-1704 CR-GGN-2016-5329 CBRCO BREAKER 152-1704 FAILS OPEN E22-CBR-C0-1704 CR-GGN-2017-12299 CBROO NORMALLY OPEN CIRCUIT BREAKER 152-1705 FAILS TO CLOSE E22-CBR-00-1705 CR-GGN-2014-873 CKVOO NORMALLY OPEN CHECK VALVE B21-F032A FAILS TffCLOSE B21-CKV-OO-F032A CR-GG N-2014-01667 CKVOO NORMALLY OPEN CHECK VALVE B21-F032B FAILS TO CLOSE B21-CKV-OO-F032B CR-GGN-2016-1308 CKVOO RCIC TURBINE EXHAUST LINE CHECK VALVE F040 FAILS TO OPEN ES 1-CKV-CC-F040 CR-GGN-2013-00689 DGN Fl DGll FAILS TO RUN DURING lST HOUR OF OPERATION P75-DGN-Fl-DG11 CR-GGN-2013-05899 DGN Fl DGll FAILS TO RUN DURING lST HOUR OF OPERATION P75-DGN-F1-DG11 CR-GGN-2015-6831 DGN Fl DG12 FAILS TO RUN DURING lST HOUR OF OPERATION P75-DGN-Fl-DG12 CR-GGN-2013-03423 DGN Fl Diesel Generator Fails to Run During First Hour of Operation P75E001A GGCR-2007-00378 DGN FS DG12 FAILS TO START P75-DG N-FS-DG 12 CR-GGN-2014-7826 DGN FS DG12 FAILS TO START P75-DG N-FS-DG 12 CR-GGN-2016-04410 EPVCC NORMALLY CLOSED EXPLOSIVE VALVE C41-F004B FAILS TO OPEN C41-EPV-CC-F004B CR-GGN-2015-4832 FNS FR UNIT 2 TRAIN A EXHAUST SIDE FAN 2277-COOlA FAILS TO RUN Z77-FNS-Fl-2C01A-S CR-GGN-2014-05317 FNS FR UNfT 1 TRAIN A SUPPLY SIDE FAN 1277-BOOlA FAILS TO RUN Z77-FNS-FR-B001A-S CR-GGN-2015-01927 FNS FS Fan Fails to Start 1Z77C001B GGCR-2010-01870 MCSFS Standby Air Compressor 1P47C002A Fails to Start P4 7-MCS-FS-C002A CR-GGN-2012-09653

ENTGGGX083-RPT-001 Data Sensitivity Study Page 113 of 132 Type Code Description Component Plant Documentation MDC FR Air Compressor C001A Fails to Continue Running P51-MDC-FR-C001A CR-GGN-2011-02091 MDC FR PS PLANT AIR COMPRESSOR C001A FAILS TO CONTINUE RUNNING P51-MDC-FR-C001A-P CR-GGN-2013-06508 MDC FR PS PLANT AIR COMPRESSOR C001A FAILS TO CONTINUE RUNNING P51-MDC-FR-C001A-P CR-GGN-2013-5153

/

MDC FR PS PLANT AIR COMPRESSOR C001A FAILS TO CONTINUE RUNNING P51-MDC-FR-C001A-P CR-GGN-2013-7038 MDC FR PS PLANT AIR COMPRESSOR C001A FAILS TO CONTINUE RUNNING P51-MDC-FR-C001A-P CR-GGN-2014-6114 MDC FR PS PLANT AIR COMPRESSOR C001A FAILS TO CONTINUE RUNNING P51-MDC-FR-C001A-P CR-GGN-2015-1582 MDC FR PS PLANT AIR COMPRESSOR COOlA FAILS TO CONTINUE RUNNING P51-MDC-FR-C001A-P GGCR-2012-11043 MDC FR Air Compressor COOlB Fails to Continue Running P51-MDC-FR-C0018 CR-GGN-2010-08815 MDC FR Air Compressor COOlB Fails to Continue Running P51-MDC-FR-C001B CR-GGN-2012-00005 MDC FR PS PLANT AIR COMPRESSOR C001B FAILS TO CONTINUE RUNNING P51-MDC-FR-C001B-P CR-GGN-2017-5917 MDC FR PS PLANT AIR COMPRESSOR COOlC FAILS TO CONTINUE RUNNING P51-MDC-FR-C001C-P CR-GGN-2013-5209 MDC FR PS PLANT AIR COMPRESSOR COOlC FAILS TO CONTINUE RUNNING P51-MDC-FR-C001C-P GGCR-2012-10982 MDCFS AIR COMPRESSOR COOlB FAILS TO START PSl-MDC-FR-COOlB-P CR-GGN-2014-4274 MDCFS AIR COMPRESSOR COOlC FAILS TO START PSl-MDC-FR-COOlC-P CR-GGN-2015-4584 MDP FR CONDENSATE BOOSTER MOTOR DRIVEN PUMP N19-C002B FAILS TO RUN N 19-MDP-FR-C002B CR-GGN-2017-1486 MDP FR CONDENSATE BOOSTER MOTOR DRIVEN PUMP N19-C002C FAILS TO RUN N19-MDP-FR-C002C CR-GGN-2017-1956 MDP FR MOTOR DRIVEN PUMP N71-C001A FAILS TO RUN N71-MDP-FR-C001A CR-GGN-2013-07211 MDS FR MOTOR-DRIVEN PUMP C002A FAILS TO CONTINUE RUNNING E12-MDS-FR-C002A CR-GGN-2017-8434 MDS FS STANDBY MOTOR DRIVEN PUMP P41-C002 FAILS TO RUN IN FIRST HOUR 52-170124 CR-GGN-2013-7426 MDS FS HPCS MOTOR DRIVEN PUMP COOl FAILS TO START E22-MDS-FS~C001 CR-GGN-2018-7762 MOD CC MOD 1Y47-F001A FAILS TO OPEN Y47-MOD-CC-F01AA CR-GGN-2016-05211 MOD CC MOD 1Y47-F001B FAILS TO OPEN Y4 7-MOD-CC-FOlBB CR-GGN-2017-07635 MOD CC MOD 1Y47-F002A FAILS TO OPEN Y47-MOD-CC-F02AA CR-GGN-2014-08441 MOD CC MOD 1Y47-F002A FAILS TO OPEN Y47-MOD-CC-F02AA CR-GGN-2014-8155 MOD CC MOD 1Y47-F002A FAILS TO OPEN Y4 7-MOD-CC-F02AA CR-GGN-2015-0342 MOD CC MOD 1Y47-F002B FAILS TO OPEN Y47-MOD-CC-F02BB CR-GGN-2013-02932

ENTGGGX083-RPT-001 Data Sensitivity Study Page 114 of 132 Type Code Description Component -

Plant Documentation MOD CC MOD 1Y47-F002B FAILS TO OPEN Y47-MOD-CC-F02BB CR-GGN-2015-00745 MOVCC Minimum Flow Valve F012-C Fails to Open E22-MOV-CC-F012 CR-GGN-2011-01911 MOVOC MOTOR-OPERATED VALVE F048A PLUGS E12-MOV-OC-F048A CR-GGN-2018-9705 MOVOC NORMALLY OPEN MOTOR DRIVEN VALVE E51F063 FAILS CLOSED E51-MOV-OC-F063 CR-GGN-2013-07720 MOVOC NORMALLY OPEN MOTOR DRIVEN VALVE E51F064 FAILS CLOSED E51-MOV-OC-F064 CR-GGN-2015-1532 MOVOC NORMALLY OPEN MOTOR DRIVEN VALVE E51F064 FAILS CLOSED E51-MOV-OC-F064 CR-GGN-2015-1677 MOVOO NORMALLY OPEN MOTOR DRIVEN VALVE F003B FAILS TO CLOSE E61-MOV-OO-F003B CR-GGN-2017-10756 MOVOO SSW Recirc Valve F006B Fails to Close P41-MOV-OO-F006B CR-GGN-2012-05598 PTR LP SERVICE TRANSFORMER 21 HARDWARE FAILURE R15-PTR-LP-SVC21 CR-GGN-2016-5153 TDP FR MAIN FEEDWATER TURBINE DRIVEN PUMP N21-C001B FAILS TO RUN N21-TDP-FR-C001B-F CR-GGN-2012-12487 TDS FS RCIC TURBINE-DRIVEN PUMP FAILS TO START E51-TDS-FS-C001-R CR-GGN-2014-00146 TDS FS RCIC TURBINE-DRIVEN PUMP FAILS TO START E51-TDS-FS-C001-R CR-GGN-2014-7810 TIMDD DIVISION 1 (A) 105 SEC TIMER 821-KSA FAILS 821-TIM-DD-KSA CR-GGN-2017-1939 TIMDD DIVISION 1 (A) 105 SEC TIMER 821-KSA FAILS 821-TIM-DD-KSA CR-GGN-2017-5374

ENTGGGX083-RPT-001 Data Sensitivity Study Page 115 of 132 Appendix G - Runtime and Demand Estimates (September 1, 2006-August 31, 2018)

ENTGGGX083-RPT-001 Data Sensitivity Study Page 116 of 132

\_

Type Demands Description Distribution Notes on Update Method Code or Hours Comp Dem and Exp - Sens.xlsx: Update AOV CC AOVCC Air-Operated Valve Fails to Open B 86 worksheet with new BE list and rx crit. time Comp Dem and Exp - Sens.xlsx: Update AOV OC AOVOC Air-Operated Valve Transfers Closed G 4785372 worksheet with new BE list and rx crit. time Comp Dem and Exp - Sens.xlsx: Created ASL ON ASLDN Level Transmitter Fails on Demand B 1740 worksheet with BE list assuming quarterly test Comp Dem and Exp - Sens.xlsx: Created ASP DN ASP DN Pressure Transmitter Fails on Demand B 2144 worksheet with BE list assuming quarterly test BAT LP Battery Fails to Operate G 630864 App c-1.xls time= 315432 hrs

2 - 630864 hours Comp Dem and Exp - Sens.xlsx: Created CBR CC CBR CC Circuit Breaker Fails to Open B 96 worksheet with BE list assuming outage test Comp Dem and Exp - Sens.xlsx: Created CBR CO CBRCO Circuit Breaker Fails to Remain Closed G 15153679 worksheet with new BE list and rx crit. time Comp Dem and Exp - Sens.xlsx: Created CBR 00 CBROO Circuit Breaker Fails to Close B 116 worksheet with BE list assuming outage test Not a single CKV 00 BE was risk significant in FPIE, so will CKVOO Check Valve Fails to Close B N/A not update.

Diesel Generator Fails to Run During the App c-1.xls: Assume same as number of starts for DGN FS DGN Fl G 2802 First Hour App c-1.xls: Assume starts from 9/2006 - 8/2012 same as DGN FS Diesel Generator Fails to Start B 2802

/ from 9/2012 - 8/2018 Comp Dem and Exp - Sens.xlsx: Update EPV CC EPV CC Explosive Valve Fails to Open B 10 worksheet with new BE list and rx crit. time Fan (Standby) Fails to Run After the First App c-1.xls: Assume runtime from 9/2006 - 8/2012 same FNS FR G 958780 Hour as from 9/2012 - 8/2018 App c-1.xls: Assume starts from 9/2006 - 8/2012 same as FNS FS Fan (Standby) Fails to Start B 11371 from 9/2012 - 8/2018 Motor-Driven Air Compressor (Standby) Comp Dem and Exp - Sens.xlsx: Update MCS FS MCS FS B 445 Fails to Start worksheet with new BE list and rx crit. time App c-1.xls: Assume 1 comp runs constantly with 2nd MDC FR P Motor-Driven Air Compressor Fails to Run G 94821 comp 7% of critical yr

ENTGGGX083-RPT-001 Data Sensitivity Study Page 117 of 132 Type Demands Description Distribution Notes on Update Method Code or Hours Motor-Driven Air Compressor Fails to App c-1.xls: Assume starts from 9/2006 - 8/2012 same as MDC FS P B 451 Start from 9/2012 - 8/2018 App c-1.xls: Assume runtime from 9/2006 - 8/2012 same MDP FR Motor-Driven-Pump Fail to Run G 3235768 as from 9/2012 - 8/2018 Motor-Driven Pump (Standby) Fails to Run App c-1.xls: Assume runtime from 9/2006 - 8/2012 same MDSFR G 20668 After the First Hour as from 9/2012 - 8/2018 Motor-Driven Pump (Standby) Fails to App c-1.xls: Assume starts from 9/2006 - 8/2012 same as MDSFS B 1677 Start from 9/2012 - 8/2018 App c-1.xls: Est. on Y47 & X77 Fan starts. Assume starts MOD CC Motor-Operated Damper Fails to Open B 10507 from 9/06 - 8/12 same as 9/12 - 8/16 Comp Dem and Exp - Sens.xlsx: Update MOV CC MOVCC Motor-Operated Valve Fails to Open B 3404 worksheet with new BE list and rx crit. time Comp Dem and Exp - Sens.xlsx: Update MOV CO MOVOC Motor-Operated Valve Transfers Closed G 7266677 worksheet with new BE list and rx crit. time Comp Dem and Exp - Sens.xlsx: Update MOV 00 MOVOO Motor-Operated Valve Fails to Close B 1634 worksheet with new BE list and rx crit. time -

App c-1.xls: Assume runtime from 9/2006 - 8/2012 same PTR LP Transformer Fails to Function G 3680044 as from 9/2012 - 8/2018 App c-1.xls: Assume runtime from 9/2006 - 8/2012 same TDP FR Turbine Driven Pump Fail to Run G 201600 as from 9/2012 - 8/2018 RCIC Turbine-Driven Pump (Standby) Fails App c-1.xls: Assume startsfrom 9/2006 - 8/2012 same as TDS FS B 381 to Start from 9/2012 - 8/2018 Comp Dem and Exp - Sens.xlsx: Created TIM DD TIMDD Timer Fails to Operate G 974798 worksheet with BE list and rx crit. Time

ENTGGGX083-RPT-001 Data Sensitivity Study Page 118 of 132 Appendix H - GGNS_R4B-Rel-Sens.rr Bayesian Data

ENTGGGX083-RPT-001 Data Sensitivity Study Page 119 of 132 Prior Prior Prior Exp TC Rate l)nit Description Dist Variance Prior Source FF Exposure Dist Mean Var. Units Air-Operated NU REG/CR-AOVCC 1.68E-03 N Valve@@@@ B 1.34E-06 B 9.SlE-04 8.llE-07 1 86 N 6928 v2010 Fails to Open Air-Operated N_UREG/CR-AOVOC 3.68E-07 H Valve@@@@ G 3.67E-14 G 1.31E-07 2.SOE-14 3 4785372 H 6928 v2010 Transfers Closed Level Transmitter NU REG/CR-ASL DN 1.14E-03 N @@@@ Fails on B 6.31E-07 B 8.lSE-04 1.30E-05 2 1740 N 6928 v2010 Demand Pressure Transmitter NU REG/CR-.

ASP DN 4.08E-04 N B 1.59E-07 B 1.17E-04 2.72E-07 1 2144 N

@@@@ Fails on 6928 v2010 Demand Battery @@@@ NU REG/CR-BAT LP 7.SOE-07 H G 1.95E-13 G 5.86E-07 1.82E-13 *1 630864 H Fails to Function 6928 v2010 Circuit Breaker NU REG/CR-CBRCC 5.95E-03 N @@@@ Fails to B 1.19E-05 B 2.39E-03 5.93E-06 2 96 N 6928 v2010 Open Circuit Breaker NU REG/CR-CBRCO 1.04E-07 H @@@@ G 5.07E-15 G 2.llE-07 3.86E-14 1 15153679 H 6928 v2010 Transfers Open Circuit Breaker NU REG/CR-CBROO 3.79E-03 N @@@@ Fails to B 7.28E-06 B 2.39E-03 5.93E-06 1 116 N 6928 v2010 Close Diesel Generator

@@@@ Fails to NU REG/CR-DGN Fl 3.42E-03 H G 1.87E G 3.78E-03 2.44E-07 4 2802 H Run During the 6928 v2010 First Hour

ENTGGGX083-RPT-001 Data Sensitivity Study Page 120 of 132 Prior Prior Prior Exp TC Rate Unit Description Dist Variance Prior Source FF Exposure Dist Mean Var. Units Diesel Generator NU REG/CR-DGN FS 1.80E-03 N @@@@ Fails to B 3.21E-07 B 2.89E-03 1.03E-06 2 2802 N 6928 v2010 Start Explosive Valve NUREG/CR-EPVCC 4.21E-03 N @@@@ Fails to B 7.04E-06 B 2.57E-03 4.38E-06 1 10 N 6928 v2010 Open Fan {Standby)

@@@@ Fails to NU REG/CR-FNS FR 6.lSE-06 H G 5.81E-12 G 4.54E-05 4.58E-10 2 958780 H Run After the 6928 v2010 First Hour Fan {Standby)

NU REG/CR-FNS FS 6.78E-04 N @@@@ Fails to B 1.29E-08 B 8.42E-04 2.0SE-08 1 11371 N 6928 v2010 Start Motor-Driven Air Compressor NU REG/CR-MCS FS 3.31E-03 N (Standby) B 6.87E-06 B l.71E-02 4.76E-04 1 445 N 6928 v2010

@@@@ Fails to Start Motor-Driven Air MDC FR Compressor NU REG/CR-l.18E-04 H G 9.99E-10 G 8.SOE-05 3.61E-09 12 94821 H p @@@@ Fails to 6928 v2010 Run Motor-Driven Air Compressor NU REG/CR-MDC FS P 5.33E-03 N B l.09E-05 B l.71E-02 4.76E-04 2 451 N

@@@@ Fails to 6928 v2010 Start Motor-Driven NU REG/CR-MDP FR 1.36E-06 H Pump@@@@ G 3.51E-13 G 3.53E-06 5.46E-12 3 3235768 H 6928 v2010 Fails to Run

ENTGGGX083-RPT-001 Data Sensitivity Study Page 121 of 132 Prior Prior Prior Exp TC Rate Unit Description Dist Variance Prior Source FF Exposure Dist Mean Var. Units Motor-Driven Pump (Standby)

NU REG/CR-

/

MDS FR 1.86E-05 H @@@@ Fails to G 1.95E-10 G 1.04E-05 1.39E-10 1 20668 H 6928 v2010 Run After the First Hour Motor-Driven Pump (Standby) NU REG/CR-MDS FS 1.06E-03 N B 2.83E-07 B 9.47E-04 4.61E-07 2 1677 N

@@@@ Fails to 6928 v2010 Start Motor-Operated NU REG/CR-MOD CC 6.73E-04 N Damper@@@@ B 5.30E-08 B 2.33E-04 3.SlE-08 7 6064 N 6928 v2010 Fails to Open Mot9r-Operated NU REG/CR-MOVCC 5.SlE-04 N Valve@@@@ B 9.96E-08 B 9.63E-04 4.53E-07 1 3404 N 6928 v2010 Fails to Open Motor-Operated NU REG/CR-MOVCO 1.89E-07 H Valve@@@@ G 7.85E-15 G 3.39E-08 2.0lE-15 4 7266677 H 6928 v2010 Transfers Open Motor-Operated NU REG/CR-MOVOO 1.0SE-03 N Valve@@@@ B 2.86E-07 B 9.63E-04 4.53E-07 2 1634 N 6928 v2010 Fails to Close Transformer NU REG/CR-PTR LP 4.17E-07 H @@@@ Fails to G 8.88E-14 G 9.44E-07 9.34E-13 1 3680044 H 6928 v2010 Function Main FW Turbine-Driven NU REG/CR-TDP FR 7.lOE-06 H G 1.80E-11 G 9.34E-06 4.86E-11 1 201600 H Pump@@@@ 6928 v2010 Fails to Run

ENTGGGX083-RPT-001 Data Sensitivity Study Page 122 of 132 Prior Prior Prior Exp TC Rate Unit Description Dist Variance Prior Source FF Exposure Dist Mean Var. Units RCIC Turbine-Driven Pump NU REG/CR-TDS FS R 5.60E-03 N (Standby) B l.OSE-05 B 6.49E-03 4.32E-05 2 381 N 6928 v2010

@@@@ Fails to Start Timer@@@@ NU REG/CR-TIM DD 2.SlE-06 H G 2.53E-12 G 2.48E-05 l.23E-09 2 974798 H Fails to Operate 6928 v2010

ENTGGGX083-RPT-001 Data Sensitivity Study Page 123 of 132 Appendix I - Data Source History and File Lists from Prior Models of Record

ENTGGGX083-RPT-001 Data Sensitivity Study Page 124 of 132 Item Rev3 Rev4 Rev4A Rev48 Current Sensitivity case GENERIC DATA: NUREG/CR- GENERIC DATA: NUREG/CR-6928, was the preferred 6928, was the preferred source for the generic source for the generic component failure data used _component failure data used in the GGNS PRA. This was in the GGNS PRA. This was supplemented with data from supplemented with data from GENERIC DATA: NUREG/CR- PRA-ES-01-001 and Resolution PRA-ES-01-001 and Resolution 4550 (note 20); PlANT of MCR GG-4875 for generic of MCR GG-4875 for generic SPECIFIC DATA: Primary failure rates not available in failure rates not available in source for failures is the NUREG. (Note 3) PLANT the NUREG. (Note 5) PlANT GENERIC DATA: Same as Maintenance Rule, Estimated SPECIFIC DATA: Failure data SPECIFIC DATA: Failure data Rev. 48. PLANT SPECIFIC component exposures is was collected from September was collected from September DATA: Same as Rev. 48 based on review of EPIX 1, 2006 through August 31, l, 2006 through August 31, plus failure data collected Failure Same as Rev.

reports from 2001 -2006, PDS 2012 from the GGNS 2012 from the GGNS from September 1, 2012 Data Used 4A computer data, equipment Maintenance Rule Maintenance Rule through August 31, 2018 rotation schedules, Shift Database. The data was Database. The data was from the GGNS Manager logs, system reviewed for functional reviewed for functional Maintenance Rule engineers, and PassPort tasks failures and each failure was failures and each failure was _ Database.

(note 21) Bayesian Updating reviewed to determine if the reviewed to determine if the performed when sufficient failure met the definition of a failure met the definition of a data exists failure as defined in the failure as defined in the PRA. Demand data was PRA. Demand data was --

obtained from the plant logs obtained from the plant (Note 4) Generic data logs (Note 6) Generic data updated with Plant Specific updated with Plant Specific Data when sufficient data Data when sufficient data available. available.

Failure Data 1/1/2001 - 8/31/2006 9/1/2006 - 8/31/2012 9/1/2006 - 8/31/2012 Same as Rev.

9/1/2006- 8/31/2018 period (note 20) (note 1) (note 2) 4A Covered

ENTGGGX083-RPT-001 Data Sensitivity Study Page 125 of 132 Item Rev3 Rev4 Rev4A Rev48 Current Sensitivity case Rx-Cr it Hrs for 5.30 years 46,930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months 46,930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months Same as Rev.

88,618 hours0.00715 days 0.172 hours 0.00102 weeks 2.35149e-4 months Failure (note 22) (note 7) (Note 8) 4A Data Maintenance Rule Maintenance Rule Maintenance Rule Unavailability is used for Unavailability is used for Unavailability is used for systems tracked under the systems tracked under the systems tracked under the Maintenance Rule / Maintenance Rule T&M Maintenance Rule Maintenance Rule database program. For systems not program. For systems not Same as Rev.

Unav Data program. For systems not (note 22) tracked, a review of tracked, a review of 4A used tracked, it was assumed operational history (using CR operational history (using CR that the unavailability rate database and operator logs) is database and operator logs) is over time was the same as used to determine 005 time used to determine 005 time in Rev. 48 (Note 11) (Note 11) 1/1/2001 - 8/31/2006 (note 20)

T&M Unav Data 9/1/2006 - 8/31/2012 9/1/2006 - 8/31/2012 Same as Rev.

1/1/2001 - 4/31/2005 9/1/2006 - 8/31/2018 period (note 1) (note 2) 4A (note 22) - this is believed to Covered be in error based on App F calculations Rx-Cr it Hrs for 5.30 years 46,930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months 46,930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months Same as Rev.

88,618 hours0.00715 days 0.172 hours 0.00102 weeks 2.35149e-4 months T&M (note 23) (note 9) (Note 10) 4A Unav Data

ENTGGGX083-RPT-001 Data Sensitivity Study Page 126 of 132 Item Rev3 Rev4 Rev4A Rev4B Current Sensitivity case GENERIC: NUREG-6890/EPRI Reports (Loss of Offsite GENERIC: NUREG/CR-6928 GENERIC: NUREG/CR-6928 Power, Partial Loss of Offsite (Loss of Offsite Power,, Partial (Loss of Offsite Power, Partial Power), NUREG/CR-5750 Loss of Offsite Power), Loss of Offsite Power),

{LLO~A, Intermediate LOCA, supplemented by NUREG/CR- supplemented by NUREG/CR-SLOCA), WASH-1400 for 5750 for those Initiating 5750 for those Initiating Vessel Rupture, and PRA-ES- Events not in NUREG/CR-6928 Events not in NUREG/CR-6928 01-002 Rev 1 {Loss of AC Div (small-small LOCA, CRD (small-small LOCA, CRD 1/11, Loss of DC Div 1/11) (note Reference Leg Break) and Reference Leg Break) and

18) PLANT SPECIFIC: Plant NUREG-1829 for other LOCAs , NUREG-1829 for other LOCAs specific data from last 5 years {Vessel Rupture, LLOCA, (Vessel Rupture, LLOCA,

{Transients with PCS available, Intermediate LOCA, SLOCA) Intermediate LOCA, SLOCA) Initiating events summary Loss of Feedwater); Bayesian (note 14) PLANT SPECIFIC: ( note 15) PLANT SPECIFIC: on the NRC website updated with Plant Specific Bayesian updated with Plant Bayesian updated with Plant (initiating-event-Initiating data (Transients with Loss of Specific data was used for Specific data was used for summary-2016.xlsx on Same as Events PCS, Inadvertent Closure of Turbine/Reactor Trip, Loss of Turbine/Reactor Trip, Loss of web page Rev. 4A Used MSIVs, Inadvertent Open SRV, Condenser Vacuum, Loss of Condenser Vacuum, Loss of htt~s:LLnrcoe.inl.govLresul Transients with Loss of Service Feedwater, Inadvertent Feedwater, Inadvertent tsdb/JnitEventL) and an Transformer); IEFTs (Loss of Closure of MSIVs, Inadvertent Closure of MSIVs, lnadvert.ent LER search on the NRC Plant Service Water, Loss of Open SRV, Loss of Division 1/11 Open SRV, Loss of Division 1/11 website (note 25)

Component Cooling Water, vital ac buses, Loss of Division vital ac buses, Loss of Division--,

Loss of Instrument Air, Loss of 1/11 vital de buses IEFTs were 1/11 vital de buses IEFTs were Service Transformer, Loss of used for Loss of Plant Service used for Loss of Plant Service Control Rod Drive, Loss of Water, Loss of Component Water, Loss of Component Turbine Building Cooling Cooling Water, Loss of Cooling Water, Loss of Water); Train level initiating Instrument Air, Loss of Service Instrument Air, Loss of Service for Loss of ac or de Div 1/11 Transformer, Loss of Control Transformer, Loss of Control buses are accounted for in the . Rod Drive, Loss of Turbine Rod Drive, Loss of Turbine IEFTs and loss of FW, and loss Building Cooling Water (note Building Cooling Water (note of Service Transformer 14) 15) evaluations (note 18)

ENTGGGX083-RPT-001 Data Sensitivity Study Page 127 of 132 Item Rev3 Rev4 'Rev4A Rev4B Current Sensitivity case Initiating Events 7/1/1986 - 8/30/2006. 5/22/2006 - 8/31/2012 (note 5/22/2006 - 8/31/2012 {note Same as Rev. 5/22/2006 - 8/31/2018 Data (note 19) 12) 13) 4A (note 26) period Covered Rx-Cr it Hrs for 17.96 years 49,188.06 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 49,188.06 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Same as Rev.

Initiating 10.37 reactor years (note 19) (Note 16) (Note 17) 4A Events c.

Data Note 1 - From Section 2.0 of RSC 15-09 Rev 2 Note 2 - From Section 2.0 of PSA-GGNS-01-DA Rev 1 Note 3 - From Section 5.1 and Tables 3 and 5 of RSC 15-09 Rev 2 Note 4 - From Section 5.2 and Table 6 of RSC 15-09 Rev 2 Note 5 - From Section 5.1 and Tables 3 and 5 of PSA-GGNS-01-DA Rev 1 Note 6 - From Section 5.2 and Tabie 6 of PSA-GGNS-01-DA Rev 1 Note 7 - From Section 5.2 and Tables 7, 8 and 9 of RSC 15-09 Rev 2 {demands/hours used for denominator are in Table 9)

Note 8 - From Section 5.2 and Tables 7, 8 and 9 of PSA-GGNS-DA-01 Rev 1 (demands/hours used for denominator are in Table 9)

Note 9 - From Section 5.5 and Table 7 of RSC 15-09 Rev 2, and "GGNS Update Period Unavailability.xis" Note 10 - From Section 5.5 and Table 7 of PSA-GGNS-DA-01, Rev. 1, and "GGNS Update Period Unavailability.xis" Note 11- From "GGNS Unavailability.xis" Note 12 - From RSC 13-30/PSA-GGNS-01-IE, Rev 1, Section 3.3 Note 13 - From PSA-GGNS-01-IE, Rev 2, Section 3.3

ENTGGGX083-RPT-001 Data Sensitivity Study Page 128 of 132 Note 14 - From RSC 13-30/PSA-GGNS-01-IE, Rev 1, Section 3.3 and Table 9 Note 15 - From PSA-GGNS-01-IE, Rev 2, Section 3.3 and Table 9 Note 16 - From RSC 13-30/PSA-GGNS-01-IE, Rev 1, Section 3.3.1 Note 17 - From PSA-GGNS-01-IE, Rev 2, Section 3.3.1 Note 18 - From PRA-GG-01-001S06, Rev. O Sections 2 and 3 Note 19 - From PRA-GG-01-001S06, Rev O Table 4-1, Section 4.1 and Table 4-1 Note 20 - From PRA-GG-01-001S05 Rev 1, Section 1.0 Note 20 - From PRA-GG-01-001505 Rev 1, Sections 3.1.3 and 3.1.4 Note 21 - From PRA-GG-01-001505, Rev l, Section 3.1.3 and Appendices Band C Note 22 - From PRA-GG-Ol-001S05, Rev 1, Section 3.2 and Appendix F Note 23 - From PRA-GG-01-001S05, Rev 1, Appendix F, Table F-3 Note 24 - From PRA-GG-01-00lSOS, Rev 1, Appendix F, Table F-1 Note 25 - initiating-event-summary-2016. xlsx only included data up to December 2016; however, the most recent initiating event for GGNS included in the NRC summary was 6/25/2016. LRE search of NRC website was used to identify GGNS I Es from 6/25/2016 - 8/31/2018 Note 26- 5/22/2006 start date based on Rev. 4A/4B

ENTGGGX083-RPT-001 Data Sensitivity Study Page 129 of 132 Rev 3 MOR Files (PRA-GG-01-001502, Rev. 0, App A)

Model (Folder) allrulesGGR3.txt 12/17/2007 9:23:49AM 61 Rev 3 recovery rules file.

allrulet2c3.txt 11/14/2007 2:20:18 PM 61 Same as above.

FGMASTGGR3.CAF 7/31/2007 11:21:20AM 7 Master flag file for Rev 3.

GGMutexcR3.txt 5/4/2007 2:47:47 PM 6 Mutually exclusive file for Rev 3.

GGNSR3 1E-12rec.qnt 12/17/2007 9:30:57 AM 45 Praquant control file for Rev 3.

GGNSR3.RR 11/16/2007 12:58:33 PM 2956 Rev 3 data base.

GGR3 lE-12 baseline.cut 11/15/2007 7:47:16AM 11856 Quantified and recovered cutset file with sequence and RCIC failure flags subsumed. This is considered the baseline cutset file for the Rev 3 update.

ggr3.caf 10/18/2007 10:08:03AM 271 Rev 3 fault tree.

ggr3modules.cut 9/20/2007 6:05:39AM 224 Cutset file of Rev 3 modules.

ENTGGGX083-RPT-001 Data Sensitivity Study Page 130 of 132 Rev-4 MOR Files (RSC 16-09/PSA-GGNS-01-QU-0 1, Rev 0, Att A)

Model Files:

Narne Date m-odified Type Size

~ GGNS_MOR_R4JF.rr 3/24/20113:54 PM CAFTA Database 75,020 KB

{a GGNS_MOR_R4_NoModJF.caf 3/22/2017 3:10 PM CAFTA Fault Tree 757 KB Flag File:

Name [}ate modified

Type Size FLG_GGNS_R4.txt 12/12/2016 8:43 AM Text Document 1 KB Recovery Rule Files:

Narne Date modified Type Size GGNS FLOOD CUTSETS.txt 2/14/201711:21 AM Ted Document 1 KB GGNS INTERNAL EVENT CUTSETS.txt 2/14/201711:21 AM Te:1t Docurnent 2K8 GGNS_MORJFCDF_R4f_ALL.txt 3/23/2017 ;1.2:12 Pfv1 Ted Document 122 KB GGNS_MOR_LERF_R4_HFE.txt 3/23/2017 2:47 Pfv1 Text: Docurnent 158 KB GGNS_MOR_R4_LOSP.b.t 11/17/201611;;25 .. , Text Document

ENTGGGX083-RPT-001 Data Sensitivity Study Page 131 of 132 Rev 4A MOR Files (PSA-GGNS-01-QU, Rev 2, Att A)

Model Files:

. FI..G_GGNS_R4A-NOFlEX.txt 7/5/20l7 7:32 Afvt Ta1 Da.rnm1::nt: 1 KB GG[\IS INTERNAL EVENT CUTSETS.txt 7/25/2017 9:35 Af./t Text Document nrn GGNS Rev 4a CDF w LOOP ..b.t 1/19/2017 9:41 AIM T e..xt Document KB

. GGNS Rev4a LERFw lOOP.trt 7/20/2017 8:03 AJ,,,1 Text Docun1cnt KB ti) GGNS_R4A.rr 7/25/2{1171:18 P~./l CAFTA-Database 3,712 KB I) GGNS_R4A_Seq-new IF.caf 7/2.5./20l712:41 Pf\,1 CAFTA Fault Tree KB (I GGNS_R4A-new IF.caf 7/25/2:0l712:3H Pr>l1 CAFTA Fault tree

ENTG GGX083-RPT-001 Data Sensitivity Study

Page 132 of 132 Rev 48 MOR Files (PSA-GGNS-01 Rev 1, Att 7)

FLG~GGNS_R4B-NOFLEX.txt 7/5/2:017 7:32 AM Text Document 1 KB GGNS Rev4B LERFw LOOP- IE Only.txt 1'1/1/2018 .2:4D PM T e.'<t Docurnent GGNS Rev 4B CDF w LOOP.trt 11/1/2018 191 KB GGNS Rev4B LERFw LOOP- IF Only.txt 109 KB GGNS Rev48 LERFw LOOP.trt Text DooJment 1 KB GGNS Rev 48 CDF w LOOP - IF only . M 191 KB FlG_GGNS_NOFLOOD.txt 11/1/20184:58 Pfv1 Text Dornrnent 2KB GGMS Rev4B CDF1,v LOOP- IE onl)'.txt 11/1/2018 5:24 Pr*,,1 Text Docurnent 1

~ GGNS_R4B.rr 11/18/2.018 3:19 PJA CAFTA Database

~ GGNS_R4B-new IF.ca.f 11/18/2.018 3:17 Pfv1 C;AFTA Fault Tree 7H4KB IJ GGNS_R4B-new IF_Seq.caf *11/.18/20.18 3:*19 Pfvl CA.FTA Fault Tree KB

v t e Letter Sequence Other
EPID:L-2018-LLA-0106, TSTF-425 (Approved, Closed)
Initiation Acceptance Supplement Administration Questions Answers 30 November 2018 Results Approval Other: GNRO-2019/00012, Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
MONTHYEAR2018-06-07 [Table View]

GNRO-2019/00012, Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program

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