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 ; (NPF-029)
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 GNR0-2019/00012 March 06, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 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

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)

Originator:

Gregory P. Rozga Digit.lily signed by 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 Steve Phillippi

-ff.:~---:;:.:~~tt*<:::::-

D1!ijt~!ly ~ig:Md by Stn'en ~hlilii'J.,.

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

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t>1,,.ail"'H>hi!t1ppk~n~n:c11tr.cim. r.... ll:i Dat<r.2019.01.1117:l&*U*CS'OO' Approver:

Diane Jones

,,..r~)r";

Digirally signed by Diane M. Jones Date:

January 2019 ON: cn=Oiane M. Jones, o=Enercon ~rvices, Inc., ou=PRA, email=djones:~~nercon.com, 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 Page 2 of 132 Table of Contents Data Sens.itivity Study 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 Page 3 of 132 1.0 Scope Data Sensitivity Study 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-status/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 January 336 744 744 744 72 February 672 216 504 456 672 March 744 312 744 96 744 April 720 720 720 720 480 May 744 744 744 744 744 Ju nae 720 720 720 552 720 July 720 744 744 312 744 August 696 744 744 744 696 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 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 Total operating years 41688 4.76 hrs yrs 2018 552 624 744 144 0

0 480 744 3288

ENTGGGX083-RPT-001 Page 4 of 132 Data Sensitivity Study 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 Page 5 of 132

%T3B PROB 2.37E-01 Data Sensitivity Study 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.xlsx 11 [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 Page 6 of 132 Data Sensitivity Study 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 N 19-HTX-MA-B003C L20-BAT-MA-1H2 L51-BCC-MA-1K4 N 19-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 events are not significant events. 1 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 Page 7 of 132 Data Sensitivity Study 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 Page 8 of 132 Data Sensitivity Study 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 spreadsheet was adapted from spreadsheet "GGNS Plant Component Demands and Exposures.xlsx 1

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

CDF.CUT Cutset File 1/4/2019 4:30 PM 12,578 KB I

The results of the quantification are provided below:

Case Results Base CDF 2.58E-06 Sensitivity CDF

2.96E-06 Base LERF 7.74E-07, Sensitivity LERF 9.38E-07 7.0 Results and Conclusions Data Sensitivity Study I LERF I

LERF.CUT 1/4/2019 4:47 PM 21,910 KB Increase

% Increase 3.80E-07 14.7%

1.64E-07 21.2%

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 Page 11 of 132 Data Sensitivity Study 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 Page 12 of 132 Appendix A - GGNS Initiating Event LER Data (September 1, 2012 -August 31, 2018)

Data Sensitivity Study

E NTGGGX083-RPT-001 Page 13 of 132 LER Number Event Date 4162012008 12/29/2012 NRC Code Code Description QRS Turbine Trip

/

Data Sensitivity Study Abstract Mapped GGNS IE On December 29, 2012, at 00:18 Central Standard Time, Grand Gulf Nuclear

%T3A 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 Page 14 of 132 LER Number Evenn:>ate 4162013001 1/4/2013 NRC Code Code Description QRS Turbine Trip Data Sensitivity Study Abstract Mapped GGNS IE At 23:37 Central Standard Time on January 4, 2013, Grand Gulf Nuclear Station

%T3A 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.

E NTG GGX083-RPT-001 Page 15 of 132 LER Number Event Date 4162013002 1/14/2013 NRC Code Code Description QR5 Turbine Trip l

Data Sensitivity Study Abstract Mapped GGNS IE At 18:05 Central Standard Time on Januariy 14, 2013, Grand Gulf Nuclear

%T3A 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 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.

E NTG GGX083-RPT-001 Page 16 of 132 LER Number Event Date 4162013003 7/30/2013 NRC Code Code Description QRS Turbine Trip Data Sensitivity Study Abstract Mapped GGNS IE At 14:32 Central Daylight Time on July 30, 2013, Grand Gulf Nuclear Station

%T3A 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 Page 17 of 132 LER Number Event Date 4162014002 3/17/2014 NRC Code Code Description QR6 Manual Reactor Trip Data Sensitivity Study Mapped Abstract GGNS IE On March 1?, 2014, at 05:14 Central Daylight Time with the plant at 41

%T2 percent rated core thermal power during power ascension from refueling 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.

E NTGGGX083-RPT-001 Page 18 of 132 LER Number Event Date 4162014003 3/29/2014 NRC Code Code Description QRS Turbine Trip Data Sensitivity Study Abstract Mapped GGNS IE On March 29, 2014, at 10:08 Central Daylight Time with the plant at 87

%T3A 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 Page 19 of 132 LER Number Event Date 4162015001 2/7/2015 NRC Code Code Description QR5 Turbine Trip Data Sensitivity Study Abstract Mapped GGNS IE 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 plant at 100 percent thermal power, Grand Gulf Nuclear Station experienced an automatic actuation of the reactor protection system (RPS) and subsequent reactor SCRAM. The 118 11 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 transformer and control cabinet on 11 8 11 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 Page 20 of 132 LER Number Event Date 4162016002 3/29/2016 4162016004 6/17/2016 NRC Code QRS QR4 Code Description Turbine Trip Core Power Excursion (RPS Trip)

Data Sensitivity Study Abstract Mapped GGNS IE On March 29, 2016, at 1123 Central Daylight Time, Grand Gulf Nuclear Station

%T3A was operating in Mode 1 and ascending in power at approximately 37% when an unplanned uncomplicated automatic reactor SCRAM occurred. A generator lockout was received due to a Main Transformer 18 1 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 functioned as designed. The cause of the Main Transformer 18 1 Differential Relay Trip was identified during forced outage investigation of the 18 1 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 wiring configuration was corrected and all remaining wiring for the 'A',

18 1

, 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.

On June 17, 2016, at 0256 Central Daylight Time, Grand Gulf Nuclear Station

%T3A experienced an automatic reactor scram. Prior to the scram, Grand Gulf Nuclear Station was operating in Mode 1 at approximately 65% rated thermal power and performing the Turbine Stop and Control Valve Operability Surveillance. During the surveillance, after the 18 1 Turbine Stop valve was 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.

E NTG GGX083-RPT-001 Page 21 of 132 LER Number Event Date 4162016005 6/25/2016 NRC Code Code Description QR5 Turbine Trip Data Sensitivity Study Abstract Mapped GGNS IE On June 25, 2016, at 1407 Central Daylight Time, Grand Gulf Nuclear Station

%T3A 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 Page 22 of 132 LER Number Event Date 4162016007 9/8/2016

\\

NRC Code Code Description QR6 Manual Reactor Trip Data Sensitivity Study Abstract Mapped GGNS IE Technical Specification Shutdown Because of the Loss of the Residual Heat

%T3A Removal Pump. On September 4, 2016 at 02:58, Grand Gulf Nuclear Station 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 Page 23 of 132 LER Number Event Date 4162017003 4/4/2017 NRC Code Code Description QR6 Manual Reactor Trip Data Sensitivity Study Abstract Mapped GGNS IE Reactor Shutdown Because of Condensate System Inventory Depletion and a

%T3B Manual Reactor Core Isolation Cooling (RCIC) Initiation Because of Feedwater 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.

E NTG GGX083-RPT-001 Page 24 of 132 LER Number Event Date 4162017006 8/29/2017 NRC Code Code Description QR6 Manual Reactor Trip Data Sensitivity Study Abstract Mapped GGNS IE Completion of Grand Gulf Nuclear Station Shutdown Requ'ired By Technical

%T3A Specifications Because of an Inoperable A Residual Heat Removal Pump. On 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 Page 25 of 132 LER Number Event Date 4162018001 1/30/2018 NRC Code Code Description QR6 Manual Reactor Trip Data Sensitivity Study Abstract Mapped GGNS IE Reactor Manual Shutdown due to Turbine Pressure Control Valve Position

%T3A Changes. On January 30, 2018, Grand Gulf Nuclear Station (GGNS) was 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 Page 26 of 132 Data Sensitivity Study Appendix B - Bayesian Update Worksheet for Initiating Events

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

ENTGGGX083-RPT-001 Page 31 of 132 Event Name Cll-MDP-MA-COOlA Cll-MDP-MA-COOlB C41-TRN-MA-TRNA C41-TRN-MA-TRNB El2-TRN-MA-RHRA El2-TRN-MA-RHRB 005 Hours Description 9/1/06-8/31/18 STANDBY PUMP 620.75 Cll-COOlA UNAVAILABLE DUE TO TEST OR MAINTENANCE STANDBY PUMP 380.33 Cll-COOlB IS UNAVAILABLE DUE TO TEST OR MAINTENANCE SLC PUMP TRAIN A 341.99 UNAVAILABLE DUE TO MAINTENANCE SLC PUMP TRAIN B 410.99 UNAVAILABLE DUE TO MAINTENANCE RHR TRAIN A 1097.78 UNAVAILABLE DUE TO MAINTENANCE RHR TRAIN B 607.90 UNAVAILABLE DUE TO MAINTENANCE

~

Data Sensitivity Study Exp. Hours T/M Original Rev. 4A 9/1/06-Sensitivity Case Notes 8/31/18 Unavail.

Notes 88618.01 7.00E-3 Sheet 11Cll Hours" 88618.01 4.29E-3 Sheet 11Cll Hours"

~

88618.01 3.86E-3 Sheet 11C41 Hours" 88618.01 4.64E-3 Sheet 11C41 Hours 11 105192.00 l.04E-2 Sheet 11E12 Hours" 105192.00 5.78E-3 Sheet 11E12 Hours"

ENTGGGX083-RPT-001 Page 32 of 132 Event Name E12-TRN-MA-RHRC E21-MDP-MA-C001 E22-MOV-MA-F023 E22-MOV-MA-FlOll Description RHR TRAIN C UNAVAILABLE DUE TO MAINTENANCE LPCS SYSTEM UNAVAILABLE DUE TO TESTING/

MAINTENANCE TEST LINE IN OPERATION--VALVE F023-C OPEN TEST LINE IN OPERATION--VALVES FOlO-C & FOll-C OPEN OOS Hours 9/1/06-8/31/18 431.01 286.78 0.00 0.00 Data Sensitivity Study Exp. Hours T/M Original Rev. 4A 9/1/06-Sensitivity Case Notes 8/31/18 Unavail.

Notes 105192.00 4.lOE-3 Sheet 11El2 Hours" 105192.00 2.73E-3 Sheet 11E21, E22 Hours" 105192.00 O.OOE+OO There was no data provided in sheet "E22 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).

105192.00 O.OOE+OO There was no data provided in sheet "E22 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).

ENTGGGX083-RPT-001 Page 33 of 132 Event Name E22-SYS-MA-HPCS P81-DGN-MAlll-DG13 E30-MOV-MA-SPMUA J

E30-MOV-MA-SPMUB E51-TDP-MA-C001 L20-BAT-MA-1H1 OOS Hours Description 9/1/06-8/31/18 HPCS UNAVAILABLE 908.14 DUE TO MAINTENANCE PS DIESEL GEN. 13 1251.43 OUT FOR MAINTENANCE SPMU TRAIN A 106.63 VALVES UNAVAILABLE DUE TO MAINTENANCE SPMU TRAIN B 145.75 UNAVAILABLE DUE TO MAINTENANCE RCIC UNAVAILABLE 991.93 DUE TO MAINTENANCE 24V DC BATIERY 14.00 1Hl UNAVAILABLE DUE TO TEST OR MAINTENANCE Data Sensitivity Study Exp. Hours T/M Original Rev. 4A 9/1/06-Sensitivity Case Notes 8/31/18 Unavail.

Notes 88618.01 1.02E-2 Sheet "E21, E22 Hours" 88618.01 1.41E-2 Sheet "P75 Hours" 88618.01 1.20E-3 Sheet "E30 Hours" 88618.01 1.64E-3

Sheet 11E30 Hours" 88618.01 l.12E-2 Sheet 11E51 Hours" 105192.00 l.33E-4 MCR GG-4962 There was no data provided for this system. _Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Page 34 of 132 Event Name L20-BAT-MA-1J 1 L20-BAT-MA-1 H2 L20-BAT-MA-1J2 Description 24V DC BATTERY lJl UNAVAILABLE DUE TO TEST OR MAINTENANCE 24V DC BATTERY 1H2 UNAVAILABLE DUE TO TEST OR MAINTENANCE 24V DC BATTERY 1J2 UNAVAILABLE DUE TO TEST OR MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 14.00 105192.00 14.00 105192.00 14.00 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes l.33E-4 MCR GG-4962 There was no data provided for this system. Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

1.33E-4 MCR GG-4962 There was no data provided for this system. Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Page 35 of 132 Event Name L50-BCC-MA-1 H4 L50-BCC-MA-1J4 LSO-BCC-MA-1H5 Description BATTERY CHARGER 1H4 UNAVAILABLE DUE TO TEST OR MAINTENANCE BATIERY CHARGER 1J4 UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER lHS UNAVAILABLE DUE TO TEST OR MAINTENANCE 005 Hours Exp. Hours T/M 9/1/06-9/1/06-8/31/18 8/31/18 Unavail.

20.00 105192.00 1.90E-4 20.00 105192.00 1.90E-4 12.00 105192.00 l.14E-4 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes MCR GG-,4962 There was no data provided for this system. Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

MCR GG-4962 There was no data provided for this system. Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

ENTGGGX083-RPT-001 Page 36 of 132 Event Name L50-BCC-MA-1J5 L51-BCC-MA-1A4 L51-BCC-MA-1D4 Description BATTERY CHARGER lJS UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER 1A4 UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER 1D4 UNAVAILABLE DUE TO TEST OR MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 12.00 105192.00 0.00 105192.00 0.00 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes l.14E-4 MCR GG-4962 There was no data provided for this system. Assume OOS time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

O.OOE+OO There was no data provided in sheet 11L51 Hours" for this comporent. Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

O.OOE+OO There was no data provided in sheet 11l51 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 Page 37 of 132 Event Name LSl-BCC-MA-lAS

(

L51-BCC-MA-1D5 L51-BCC-MA-1B4 Description BATTERY CHARGER 1A5 UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER 1D5 UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER 184 UNAVAILABLE DUE TO TEST OR MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 0.00 105192.00 0.00 105192.00 b.oo 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes O.OOE+OO There was no data provided in sheet "L51 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).

O.OOE+OO There was no data provided in sheet "L51 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).

E NTGGGX083-RPT-001 Page 38 of 132 Event Name L51-BCC-MA-1E4 L51-BCC-MA-185 L51-BCC-MA-1ES Description BATTERY CHARGER 1E4 UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER 185 UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER lES UNAVAILABLE DUE TO TEST OR MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 0.00 105192.00 0.00 105192.00 0.00 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes O.OOE+OO There was no data provided in sheet "LSl Hours 11 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).

O.OOE+OO There was no data provided in sheet 11L51 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).

O.OOE+OO There was no data provided in sheet "L51 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).

ENTGGGX083-RPT-001 Page 39 of 132 Event Name L51-BCC-MA-1C4 L51-BCC-MA-1G4

. L51-BCC-MA-2G4 Description BATTERY CHARGER 1C4 UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER 1G4 UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER 2G4 UNAVAILABLE DUE TO TEST OR MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06-9/1/06-Unavail.

8/31/18 8/31/18 0.00 105192.00 O.OOE+OO r

8.00 105192.00 7.60E-5 8.00 105192.00 7.60E-5 Data Sensitivity Study Original Rev. 4A Notes Sensitivity Case Notes There was no data provided in sheet 11L51 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).

MCR GG-4962 There was no data provided in sheet 11LSl 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).

MCR GG-4962 There was no data provided

~-

in sheet 11 LSl 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).

E NTGGGX083-RPT-001 Page 40 of 132 Event Name LSl-BCC-MA-lCS LS l~BCC-MA-1 GS L51-BCC-MA-2GS Description BATTERY CHARGER.

lCS UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER lGS UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER 2GS UNAVAILABLE DUE TO TEST OR MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06 -

8/31/18 8/31/18 0.00 105192.00 12.00 105192.00 14.00 105192.00 Data Sensitivity Study T/M, Original Rev. 4A Sensitivity Case Notes Unavail.

Notes O.OOE+OO There was no data provided in sheet "LSl 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).

1.14E-4 MCR GG-4962 There was no data provided in sheet 11LSl 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).

1.33E-4 MCR GG-4962 There was no data provided in sheet "L51 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 Page 41 of 132 Event Name L51-BCC-MA-1K4 L51-B.CC-MA-1K5 L51-BCC-MA-1L4 Description BATTERY CHARGER 1K4 UNAVAILABLE DUE TO TEST OR -

MAINTENANCE BATIERY CHARGER 1K5 UNAVAILABLE DUE TO TEST OR MAINTENANCE BATTERY CHARGER 1L4 UNAVAILABLE DUE TO TEST OR MAINTENANCE OOS Hours Exp. Hours 9/1/06 -

9/1/06-8/31/18 8/31/18 172.36 105192.00 95.98 105192.00 93.98 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 1.64E-3 MCR GG-4962 There was no data provided in sheet 11LSl 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).

9.12E-4 MCR GG-4962 There was no data provided in sheet 11 LSl 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).

8.93E-4 MCR ~G-4962 There was no data provided in sheet "L51 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).

E NTG GGX083-RPT-001 Page 42 of 132 Event Name LSl-BCC-MA-lLS N19-MDP-MA-C002A N19-MDP-MA-C002B Description I

BATTERY CHARGER lLS UNAVAILABLE DUE TO TEST OR MAINTENANCE CONDENSATE BOOSTER PUMP N19-C002A UNAVAILABLE DUE TO MAINTENANCE CONDENSATE BOOSTER PUMP N19-C002B UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours 9/1/06 -

9/1/06-8/31/18 8/31/18 47.99 105192.00 86.86 88618.01 30.21 88618.01 Data Sensitivity Study T/M Original Rev. 4A Unavail.

Notes Sensitivity Case Notes 4.56E-4 MCR GG-4962 There was no data provided in sheet "L51 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).

9.SOE-4 There was no data provided in sheet "N19 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 (88618.01/46930).

3.41E-4 There was no data provided in sheet "N19 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 {88618.01/46930).

ENTGGGX083-RPT-001 Page 43 of 132 Event Name N19-MDP-MA-C002C N19-MDP-MA-C003A N19-MDP-MA-C003B Description CONDENSATE BOOSTER PUMP N19-C002C UNAVAILABLE DUE TO MAINTENANCE CONDENSATE PUMP N19-C003A UNAVAILABLE DUE TO MAINTENANCE CONDENSATE PUMP N19-C003B UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 18.88 88618.01 6.29 88618.01 6.29 88618.01 Data Sensitivity Study T/M Original Rev. 4A Unavail.-

Notes Sensitivity Case Notes 2.13E-4 There was no data provided in sheet "N19 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 (88618.01/46930).

7.lOE-5 There was no data provided in sheet "N19 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 (88618.01/46930).

7.lOE-5 There was no data provided in sheet "N19 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 {88618.01/46930).

ENTGGGX083-RPT-001 Page 44 of 132 Event Name N19-MDP-MA-C003C N19-FLT-MA-CFFFA N19-FLT-MA-CFFFB Description CONDENSATE PUMP N19-C003C UNAVAILABLE DUE TO MAINTENANCE CFFF TRAIN A UNAVAILABLE DUE TO MAINTENANCE CFFF TRAIN B UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 6.29 88618.01 66.09 88618.01 66.09 88618.01 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 7.10E-5 There was no data provided in sheet "Nl9 Hours" for this compo-nent. Assume OOS time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (88618.01/46930).

7.46E-4 There was no data provided in sheet "N19 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 (88618.01/46930).

7.46E-4 There was no data provided in sheet "N19 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 (88618.01/46930).

E NTGGGX083-RPT-001 Page 45 of 132 Event Name N19-FLT-MA-CFFFC N19-FLT-MA-CFFFD N19-FLT-MA-TRNA Description CFFF TRAIN C UNAVAILABLE DUE TO MAINTENANCE CFFF TRAIN D UNAVAILABLE DUE TO MAINTENANCE DEMINERALIZER TRAIN A UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 66.09 88618.01 66.09 88618.01 66.09 88618.01 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 7.46E-4 There was no data provided in sheet "N19 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 (88618.01/46930).

7.46E There was no data provided in sheet "N19 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 (88618.01/46930).

7.46E-4 There was no data provided in sheet "N19 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 {88618.01/46930}.

E NTGGGX083-RPT-001 Page 46 of 132 Event Name N19-FLT-MA-TRNB Nl9-FLT-MA-TRNC N19-FLT-MA-TRND Description DEMINERALIZER TRAIN B UNAVAILABLE DUE TO MAINTENANCE DEMINERALIZER TRAIN C UNAVAILABLE DUE TO MAINTENANCE DEMINERALIZER TRAIN D UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 66.09 88618.01 66.09 88618.01 66.09 88618.01 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 7.46E-4 There was no data provided in sheet "Nl9 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 (88618.01/46930).

7.46E-4 There was no data provided in sheet "N19 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 (88618.01/46930).

7.46E-4 There was no data provided in sheet 11Nl9 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 {88618.01/46930).

ENTGGGX083-RPT-001 Page 47 of 132 Event Name Nl9-FLT-MA-TRNE N19-FLT-MA-TRNF Nl9-FLT-MA-TRNG Description DEMINERALIZER TRAIN E UNAVAILABLE DUE TO MAINTENANCE DEMINERALIZER TRAIN F UNAVAILABLE DUE TO MAINTENANCE DEMINERALIZER TRAIN G UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours 9/1/06 -

9/1/06-8/31/18 8/31/18 66.09 88618.01 66.09 88618.01

~

66.09 88618.01 Data Sensitivity Study T/M Original Rev. 4A Unavail.

Notes Sensitivity Case Notes 7.46E-4 There was no data provided in sheet "N19 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 (88618.01/46930).

7.46E-4 There was no data provided in sheet 11N19 Hours 11 for 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).

7.46E-4 There was no data pr~vided in sheet 11 N19 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 (88618.01/46930).

ENTGGGX083-RPT-001 Page 48 of 132 Event Name N19-FLT-MA-TRNH N19-HTX-MA-BOOlA N19-HTX-MA-80018 Description DEMINERALIZER TRAIN H UNAVAILABLE DUE TO MAINTENANCE HEAT EXCHANGER N19-B001A UNAVAILABLE DUE TO MAINTENANCE HEAT EXCHANGER N19-B001B UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours T/M 9/1/06-9/1/06-8/31/18 8/31/18 Unavail.

66.09 88618.01 7.46E-4 86.86 88618.01 9.80E-4 30.21 88618.01 3.41E-4 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes There was no data provided in sheet "N19 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 (88618.01/46930).

Assume same There was no data provided unavailability as in sheet "N19 Hours" for respective this component. Assume 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).

Assume same There was no data provided unavailability as in sheet "N19 Hours" for I

respective this component. Assume 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}.

E NTG GGX083-RPT-001 Page 49 of 132 Event Name Nl9-HTX-MA-BOOlC N19-HTX-MA-B002A N19-HTX-MA-80028 Description HEAT EXCHANGER N19-B001C UNAVAILABLE DUE TO MAINTENANCE HEAT EXCHANGER N19-B002A UNAVAILABLE DUE Tb MAINTENANCE HEAT EXCHANGER N19-B002B UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06 -

9/1/06-8/31/18 8/31/18 Unavail.

18.88 88618.01 2.13E-4 86.86 88618.01 9.80E-4 30.21 88618.01 3.41E-4 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes

(_

Assume same There was no data provided unavailability as in sheet 11N19 Hours" for respective this component. Assume 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).

Assume same There was no data provided unavailability as in sheet 11N19 Hours 11 for respective this component. Assume 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).

Assume same There was no data provided unavailability as in sheet "N19 Hours" for respective this component. Assume 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).

E NTGGGX083-RPT-001 Page 50 of 132 Event Name N19-HTX-MA-B002C N19-HTX-MA-B003A Nl9-HTX-MA-80038 Description HEAT EXCHANGER N19-B002C UNAVAILABLE DUE TO MAINTENANCE HEAT EXCHANGER N19-B003A UNAVAILABLE DUE TO MAINTENANCE HEAT EXCHANGER N19-B003B UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06-9/1/06-8/31/18 8/31/18 Unavail.

18.88 88618.01 2.13E-4 86.86 88618.01 9.80E-4 30.21 88618.01 3.41E-4 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes Assume same There was no data provided unavailability as in sheet "N19.Hours" for respective this component. Assume 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).

Assume same There was no data provided unavailability as in sheet 11Nl9 Hours" for respective this component. Assume 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).

Assume same There was no data provided unavailability as in sheet "Nl9 Hours" for respective this component. Assume 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 Page 51 of 132 Event Name Nl9-HTX-MA-B003C N19-HTX-MA-B004A Nl9-HTX-MA-80048 Description HEAT EXCHANGER N19-B003C UNAVAILABLE DUE TO MAINTENANCE HEAT EXCHANGER N19-B004A UNAVAILABLE DUE TO MAINTENANCE HEAT EXCHANGER N19-B004B UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06-9/1/06-8/31/18 8/31/18 Unavail.

18.88 88618.01 2.13E-4 86.86 88618.01 9.80E-4 30.21 88618.01 3.41E-4 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes Assume same There was no data provided unavailability as in sheet "Nl9 Hours" for respective this component. Assume 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).

Assume same There was no data provided unavailability as in sheet 11N19 Hours 11 for respective this component. Assume 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).

Assume same There was no data provided unavailability as in sheet "Nl9 Hours" for respective this component. Assume 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 Page 52 of 132 Event Name N19-HTX-MA-B004C

(

\\

P41-CTS-MA-C003A P41-CTS-MA-C003B P41-CTS-MA-C003C P41-CTS-MA-C003D Description HEAT EXCHANGER N19-B004C UNAVAILABLE DUE TO MAINTENANCE FAN P41-C003A UNAVAILABLE DUE TO MAINTENANCE FAN P41-C0038 UNAVAILABLE DUE TO MAINTENANCE FAN P41-C003C UNAVAILABLE DUE TO MAINTENANCE FAN P41-C003D UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06 -

8/31/18 8/31/18 18.88 88618.01 528.00 105192.00 528.00 105192.00 528.00 105192.00 528.00 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 2.13E-4 Assume same There was no data provided unavailability as in sheet "N19 Hours" for respective this component. Assume 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).

5.02E-3 Per Sheet 11 P41 Hours", each SSW Fan accrues 44 hrs/yr 6os time (44 hrs/yr* 12 yrs

= 528 hrs).

5.02E-3 Per Sheet 11 P41 Hours'1, each SSW Fan accrues 44 hrs/yr 0,05 time (44 hrs/yr* 12 yrs

= 528 hrs).

5.02E-3 Per Sheet "P41 Hours", each SSW Fan accrues 44 hrs/yr 005 time (44 hrs/yr* 12 yrs

= 528 hrs).

5.02E-3 Per Sheet II P41 Hours", each SSW Fan accrues 44 hrs/yr 005 time (44 hrs/yr* 12 yrs

= 528 hrs).

ENTGGGX083-RPT-001 Page 53 of 132 Event Name P41-TRN-MA-SSW_A P41-TRN-MA-SSW_B P41-TRN-MA-ssw_c P42-MDP-MA-COOlA Description SSW TRAIN A UNAVAILABLE DUE TO MAINTENANCE SSW TRAIN B UNAVAILABLE DUE TO MAINTENANCE SSW TRAIN C UNAVAILABLE DUE TO MAINTENANCE MOTOR DRIVEN PUMP P42-C001A UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 297.65 105192.00 312.16 105192.00 491.35 88618.01 29.99 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 2.83E-3 Sheet "P41 Hours"

~

2.97E-3 Sheet "P41 Hours" 5.54E-3 Sheet "P41 Hours" 2.85E-4 Zero functional There was no data provided failures, planned in sheet 11 P42, P43 and P47 maintenance only, 2 Hours" for this component.

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}.

E NTGGGX083-RPT-001 Page 54 of 132 Event Name P42-MDP-MA-COOlB P42-MDP-MA-COOlC Description MOTOR DRIVEN PUMP COOlB UNAVAILABLE DUE TO MAINTENANCE MOTOR DRIVEN PUMP COOlC UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06-9/1/06-8/31/18 8/31/18 Unavail.

33.99 105192.00 3.23E-4 29.99 105192.00 2.85E-4 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes Zero functional There was no data provided failures, planned in sheet "P42, P43 and P47 maintenance only, 2 Hours" for this component.

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).

Zero functional There was no data provided failures, planned in sheet "P42, P43 and P47 maintenance only, 2 Hours 11 for this component.

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 Page 55 of 132 Event Name P42-HTX-MA-BOOlA P42-HTX-MA-80018 Description HEAT EXCHANGER P42-B001A UNAVAILABLE DUE TO MAINTENANCE HEAT EXCHANGER P42-B001B UNAVAILABLE DUE TO MAINTENANCE

~

005 Hours Exp. Hours T/M 9/1/06-9/1/06 -

8/31/18 8/31/18 Unavail.

29.99 105192.00 2.85E-4

~

33.99 105192.00 3.23E-4 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes Zero functional There was no data provided failures, 2 out of 3 in sheet "P42, P43 and P4 7 heat exchangers are Hours" for this component.

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).

Zero functional There was no data provided failures, _2 out of 3 in sheet "P42, P43 and P47 heat exchangers are Hours" for this component.

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).

E NTG GGX083-RPT-001 Page 56 of 132 Event Name P42-HTX-MA-BOOlC P43-HTX-MA-B001A Description HEAT EXCHANGER P42-B001C UNAVAILABLE DUE TO MAINTENANCE HEAT EXCHANGER B001A UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06 -

9/1/06-8/31/18 8/31/18 Unavail.

29.99 105192.00 2.SSE-4 1072.56 88618.01 1.21E-2 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes Zero functional There was no data provided failures, 2 out of 3 in sheet "P42, P43 and P47 heat exchangers are Hours" for this component.

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).

Zero functional There was no data provided failures, 2 out of 3 in sheet II P42, P43 and P4 7 heat exchangers are Hours" for this component.

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).

ENTGGGX083-RPT-001 Page 57 of 132 Event Name P43-HTX-MA-80018 P43-HTX-MA-BOOlC Description HEAT EXCHANGER 80018 UNAVAILABLE DUE TO MAINTENANCE HEAT EXCHANGER BOOlC UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours T/M 9/1/06-9/1/06-8/31/18 8/31/18 Unavail.

923.38 88618.01 l.04E-2 1049.90 88618.01 l.18E-2 Data Sensitivity Study Original Rev. 4A

~

Sensitivity Case Notes

Notes Zero functional There was no data provided failures, 2 out of 3 in sheet "P42, P43 and P47 heat exchangers are Hours" for this component.

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).

Zero functional There was no data provided failures, 2 out of 3 in sheet II P42, P43 and P4 7 heat exchangers are Hours" for this component.

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}.

E NTGGGX083-RPT-001 Page 58 of 132 Event Name P43-MDP-MA-C001A P43-MDP-MA-COOlB Description MOTOR DRIVEN PUMP C001A OUT DUE TO MAINTENANCE MOTOR DRIVEN PUMP COOlB OUT DUE TO MAINTENANCE 005 Hours Exp. Hours T/M 9/1/06-9/1/06-8/31/18 8/31/18 Unavail.

77.42 88618.01 8.74E-4 107.63 88618.01 1.21E-3 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes Zero functional There was no data provided failures, 2 out of 3 in sheet 11P42, P43 and P47 pumps are normally Hours" for this component.

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).

Zero functional There was no data provided failures, 2 out of 3 in sheet "P42, P43 and P47 pumps are normally Hours" for this component.

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 Page 59 of 132 Event Name P43-MDP-MA-COOlC P47-WEL-MA-WELLl Description MOTOR DRIVEN PUMP C001C OUT DUE TO MAINTENANCE RADIAL WELL 1 UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours 9/1/06 -

9/1/06-8/31/18 8/31/18 173.72 88618.01 105192.00 Data Sensitivity Study,

T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 1.96E-3 Zero functional There was no data provided failures, 2 out of 3 in sheet II P42, P43 and P4 7 pumps are normally Hours" for this component.

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).

l.OOE+OO Some of the radial Changed to 1.0; see Note 3 well UA hours seem of Table 13 of the DA very high; possibly Notebook.

adding standby time to maintenance time

E NTG GGX083-RPT-001 Page 60 of 132 Event Name P47-WEL-MA-WELL3 P47-WEL-MA-WELL4 Description RADIAL WELL 3 UNAVAILABLE DUE TO MAINTENANCE RADIAL WELL 4 UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06-9/1/06-lJnavail.

8/31/18 8/31/18 15778.40 105192.00 1.SOE-1 0.00 105192.00 O.OOE+OO Data Sensitivity Study Original Rev. 4A Notes Sensitivity Case Notes Some of the radial There was no data provided well UA hours seem in sheet "P42, P43 and P47 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).

Some of the radial There was no data provided well UA hours seem in sheet "P42, P43 and P47 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 Page 61 of 132 Event Name P47-WEL-MA-WELLS P47-WEL-MA-WELL6 Description RADIAL WELL 5 UNAVAILABLE DUE TO MAINTENANCE RADIAL WELL 6 UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours T/M 9/1/06-9/1/06-8/31/18 8/31/18 Unavail.

15778.40 105192.00 1.SOE-1 0.00 105192.00 O.OOE+OO Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes Some of the radial There was no data provided well UA hours seem in sheet "P42, P43 and P47 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).

Some of the radial There was no data provided well UA hours seem in sheet II P42, P43 and P4 7 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 8/31/18 8/31/18 Unavail.

Notes 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 Page 63 of 132 Event Name P47-MDP-MA-COOlD P47-MDP-MA-COOlE P47-MDP-MA-COOlF Description RADIAL WELL PUMP P47-C001D UNAVAILABLE DUE TO MAINTENANCE RADIAL WELL PUMP P47-C001E UNAVAILABLE DUE TO MAINTENANCE RADIAL WELL PUMP P47-C001F UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 591.18 105192.00 15.57 105192.00 7.84 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 5.62E-3 MCR GR-4904 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.

l.48E-4 MCR GR-4904 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.

7.45E-5 MCR GR-4904 There was no data provided in sheet "P42, P43 and P47 Hours". The UA was entered as a constant, and the OOS time was calculated as the UA

Exposure hours.

Assume this is still valid.

E NTGGGX083-RPT-001 Page 64 of 132 Event Name P47-MDP-MA-COOlJ P47-MDP-MA-COOlK Description RADIAL WELL PUMP P47-C001J UNAVAILABLE DUE TO MAINTENANCE RADIAL WELL PUMP P47-C001K UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours 9/1/06 -

9/1/06-8/31/18 8/31/18 499.66 105192.00 1798.78 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 4.75E-3 MCR GR-4904 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.

1.71E-2 MCR GR-4904 There was no data provided in sheet 11P42, 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.

E NTGGGX083-RPT-001 Page 65 of 132 Event Name P47-MDP-MA-COOlL

\\

P47-MDP-MA-COOlM Description*

RADIAL WELL PUMP P47-C001L UNAVAILABLE DUE TO MAINTENANCE RADIAL WELL PUMP P47-C001M UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06-9/1/06-8/31/18 8/31/18 Unavail.

14.19 54792.00 2.59E-4 0.00 54792.00 O.OOE+OO Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes MCR GR-4904 Original analysis stated pumps Land M were put into service on June 1, 2012.

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.

MCR GR-4904 Original analysis stated pumps Land M were put into service on June 1, 2012.

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 Page 66 of 132 Event Name P4 7-M CS-MA-C002A P47-MCS-MA-C002B P47-MCS-MA-C002C Description WELL 1 AIR COMPRESSOR P47-C002A UNA VAi LABLE DUE TO MAINTENANCE WELL 1 AIR COMPRESSOR P47-C002B UNAVAILABLE DUE TO MAINTENANCE WELL 3 AIR COMPRESSOR P47-C002C UNA VAi LAB LE DUE TO MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 34082.21 105192.00 1441.13 105192.00 183.03 105192.00 Dat~ Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 3.24E-1 MCR GR-4904 There was no data provided in sheet "P42, P43 and P47 Hours 11

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

Exposure hours.

Assume this is still valid.

1.37E-2 MCR GR-4904 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.

1.74E-3 MCR GR-4904 There was no data provided in sheet "P42, P43 and P47 Hours". The UA was entered as a constant, and the OOS time was calculated as the UA

Exposure hours.

Assume this is still valid.

ENTGGGX083-RPT-001 Page 67 of 132 Event Name P47-MCS-MA-C002D P47-MCS-MA-C002E P47-MCS-MA-C002F Description WELL 3 AIR COMPRESSOR P47-C002D UNAVAILABLE DUE TO MAINTENANCE WELL 5 AIR COMPRESSOR P47-C002E UNAVAILABLE DUE TO MAINTENANCE WELL 5 AIR COMPRESSOR P47-C002F UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours 9/1/06'-

9/1/06-8/31/18 8/31/18 409.20 105192.00 119.92 105192.00 1

64.06 105192.00 Data Sensitivity Study T/M Original Rev. 4A Unavail.

Notes Sensitivity Case Notes 3.89E-3 MCR GR-4904 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.

l.14E-3 MCR GR-4904 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.

6.09E-4 MCR GR-4904 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 Page 68 of 132 Event Name P47-MCS-MA-C002J P47-MCS-MA-C002K P51-MDC-MA-COOlA Description WELL4AIR COMPRESSOR P47-C002J UNAVAILABLE DUE TO MAINTENANCE WELL4AIR COMPRESSOR P47-C002K U NAVAi LAB LE DUE TO MAINTENANCE AIR COMPRESSOR COOlA UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 30400.49 105192.00 275.60 105192.00 1172.17 78888.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 2.89E-1 MCR GR-4904 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.

2.62E-3 MCR GR-4904 There was no data provided in sheet 11P42, 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.

1.49E-2 78,888 exposure hours based on time from Sept 2009 until August 2018. No data in PSl.xls for compressors for August 2018. Assume average for each month over the entire period for this month.

E NTGGGX083-RPT-001 Page 69 of 132 Event Name PSl-MDC-MA-COOlB Description AIR COMPRESSOR COOlB UNAVAILABLE DUE TO

. MAINTENANCE PSl-MDC-MA-AIR COMPRESSOR COOlC C001C UNAVAILABLE DUE TO MAINTENANCE PSl-DRY-MA-DRYA PLANT AIR DRYER A SKID OUT FOR MAINTENANCE P51-DRY-MA-DRYB PLANT AIR DRYER B SKID OUT FOR MAINTENANCE P64-E NG-MA-FIREWATER MOTOR TRNA DRIVEN PUMP TRAIN UNAVAILABLE DUE TO MAINTENANCE 005 Hours 9/1/06 -

8/31/18 705.32 2508.03 936.03 882.36 640.36 Data Sensitivity Study Exp. Hours T/M Original Rev. 4A 9/1/06-Unavail.

'Notes Sensitivity Case Notes 8/31/18 78888.00 8.94E-3 78,888 exposure hours based on time from Sept 2009-until August 2018. No data in PSl.xls for compressors for August 2018. Assume average for each month over the entire period for this month.

105192.00 2.38E-2 No data in PSl.xls for compressors for August 2018. Assume average for each month over the entire period for this month.

105192.00 8.90E-3 Original data had O hours even though Sheet "P51 Hours" included UA time.

105192.00 8.39E-3 Original data had O hours even though Sheet "P51 Hours" included UA time.

105192.00 6.09E-3 Sheet 11P64 Hours"

ENTGGGX083-RPT-001 Page 70 of 132 Event Name P64-E NG-MA-TRN B P64-MDP-MA-C002N P64-AOV-MA-TR1 P64-AOV-MA-TR2 Description FIREWATER DIESEL DRIVEN PUMP TRAIN AOUT FOR MAINTENANCE FIREWATER DIESEL DRIVEN PUMP TRAIN BOUT FOR MAINTENANCE AIR OPERATED VALVE TRAIN 1 UNAVAILABLE DUE TO MAINTENANCE AIR OPERATED VALVE TRAIN 2 UNAVAILABLE DUE TO MAINTENANCE OOS Hours 9/1/06-8/31/18 761.35 341.78 0.00 0.00 Data Sensitivity Study Exp. Hours T/M Original Rev. 4A 9/1/06 -,-

Sensitivity Case Notes 8/31/18 Unavail.

Notes 105192.00 7.24E-3 Sheet "P64 Hours" 105192.00 3.25E-3 Sheet "P64 Hours" 105192.00 O.OOE+OO There was no data provided in sheet "P64 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).

105192.00 O.OOE+OO There was no data provided in sheet "P64 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).

E NTG GGX083-RPT-001 Page 71 of 132 Event Name P64-MOV-MA-FAlOA P64-MOV-MA-FA10B P71-CHR-MA-BOOlA Description MOTOR-OPERATED VALVE FAlOA UNAVAILABLE DUE TO MAINTENANCE MOTOR-OPERATED VALVE FAlOB UNAVAILABLE DUE TO MAINTENANCE PLANT CHILLER P71-B001A UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp.'Hours 9/1/06-9/1/06-8/31/18 8/31/18 0.00 105192.00 0.00 105192.00 3961.80 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes O.OOE+OO There was no data provided in sheet 11P64 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).

O.OOE+OO There was no data provided in sheet 11P64 Hours 11 for this component. Assume OOS time is constant over time, r_

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

3.77E-2 There was no data provided in sheet 11P71 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 Page 72 of 132 Event Name P71-CHR-MA-BOOlB P71-CHR-MA-BOOlC P75-DGN-MA-DGll P75-DGN-MA-DG12 Description PLANT CHILLER P71-80018 UNAVAILABLE DUE TO MAINTENANCE PLANT CHILLER P71-BOOlC UNAVAILABLE DUE TO

~

MAINTENANCE PS DIESEL GEN. 11 OUT FOR MAINTENANCE PS DIESEL GEN. 12 OUT FOR MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 39219.11 105192.00 30289.09 105192.00 1540.65 105192.00 1693.42 105192.00 Data Sensitivity Study T/M Original Rev. 4A Unavail.

Notes Sensitivity Case Notes 3.73E-1 There was no data provided in sheet "P71 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).

2.88E-1 There was no data provided in sheet 11P71 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).

1.46E-2 Sheet 11P75 Hours" l.61E-2 Sheet 11P75 Hours"

E NTGGGX083-RPT-001 Page 73 of 132 Event Name R27-BAC-MA-EAST R27-BAC-MA-WEST Description AC BUS EAST UNAVAILABILE DUE TO MAINTENANCE AC BUS WESJ UNAVAILABILE DUE TO MAINTENANCE OOS Hours Exp. Hours 9/1/06 -

9/1/06-8/31/18 8/31/18 0.00 105192.00 0.00 105192.00 Data Sensitivity Study T/M Original Rev. 4A Unavail.

Notes Sensitivity Case Notes O.OOE+OO MCR GG-4908 There was no data provided in sheet "R27 Hours" for this 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.

0.00E+OO MCR GG-4908 There was no data provided in sheet 11R27 Hours" for this 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.

E NTG GGX083-RPT-001 Page 74 of 132 Event Name R27-TAC-MA-BAXWL R27-TAC-MA-FRANK R27-TAC-MA-PORTG

,oescription BAXTER WILSON LINE OUT OF SERVICE FRANKLIN LINE OUT OF SERVICE PORT GIBSON LINE OUT OF SERVICE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 5.87 105192.00 461.89 105192.00

~

13.00 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 5.58E-5 MCR GG-4908 There was no data provided 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).

4.39E-3 MCR GG-4908 There was no data provided 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).

l.24F4 MCR GG-4908 There was no data provided 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 Page 75 of 132 Event Name T51-CLU-MA-BOOlA T51-CLU-MA-B002A T51-CLU-MA-B003A T51-CLU-MA-80048 Description FAN COOLER T51B001-A UNAVAILABLE DUE TO MAINTENANCE FAN COOLER TS1B002-A UNAVAILABLE DUE TO MAINTENANCE FAN COOLER T518003-A UNAVAILABLE DUE TO MAINTENANCE FAN COOLER T51B004-B UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 19.94 105192.00 53.60 105192.00 47.99 105192.00 47.99 105192.00 Data Sensitivity Study T/M Original Rev. 4A Unavail.

Notes Sensitivity Case Notes 1.90E-4 Sheet "TSl Hours" 5.lOE-4 Sheet "T51 Hours" 4.56E-4 There was no data provided in sheet 11T51 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).

4.56E-4 There was no data provided in sheet "T51 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).

ENTGGGX083-RPT-001 Page 76 of 132 Event Name T51-CLU-MA-BOOSB T51-CLU-MA-B006A T51-CLU-MA-B007A Description FAN COOLER TSlBOOS-B UNAVAILABLE DUE TO MAINTENANCE FAN COOLER T51B006-A UNAVAILABLE DUE TO MAINTENANCE FAN COOLER T51B007A UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours 9/1/06-9/1/06-

~/31/18 8/31/18 47.99 105192.00 47.99 105192.00 47.99 1 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 4.56E-4 There was no data provided in sheet "T51 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).

4.56E-4 There was no data provided in sheet 11T51 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).

4.56E-4 There was no data provided in sheet "T51 Hours" for this component. Assume 005 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 Page 77 of 132 Event Name T51-CLU-MA-80078 X77-DGN-MA-DG1RM X77-DGN-MA-DG2RM X77-DGN-MA-DG3RM Y47-FNS-MA-COlAA OOS Hours Description 9/1/06 -

8/31/18 FAN COOLER 47.99 TS1B007B UNAVAILABLE DUE TO MAINTENANCE DIV I X77 SYSTEM 16.05 UNAVAILABLE (PLANNED &

UNPLANNED)

DIV 11 X77 SYSTEM 3.85 UNAVAILABLE (PLANNED &

UNPLANNED)

DIV Ill HPCS X77 24.10 SYSTEM UNAVAILABLE (PLANNED &

UNPLANNED)

SUBSYSTEM 1Y47-90.56 COOlA UNAVAILABLE DUE TO TEST OR MAINTENANCE Data Sensitivity Study Exp. Hours T/M Original Rev. 4A 9/1/06 -

Sensitivity Case Notes 8/31/18 Unavail.

Notes 105192.00 4.56E-4 There was no data provided in sheet "T51 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).

105192.00 1.53E-4 Sheet "X77, Y47 Hours" 105192.00 3.66E-5 Sheet "X77, Y47 Hours" 105192.00 2.29E-4 Sheet "X77, Y47 Hours" 105192.00 8.61E-4 Sheet "X77, Y47 Hours"

E NTGGGX083-RPT-001 Page 78 of 132 Event Name Y 4 7-FNS-MA-COlAB Y47-FNS-MA-COlBB 277-TRN-MA-SS BRA Z77-TRN-MA-SSBRB Description SUBSYSTEM 2Y47-COOlA UNAVAILABLE DUE TO TEST OR MAINTENANCE SUBSYSTEM 1Y47-COOlB UNAVAILABLE DUE TO TEST OR MAINTENANCE SSBRVS TRAIN A EQUIPMENT UNAVAILABLE DUE TO MAINTENANCE SSBRVS TRAIN B EQUIPMENT UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours 9/1/06-9/1/06-8/31/18 8/31/18 169.02 105192.00 139.79 88618.01 331.66 105192.00 1875.23 105192.00 Data Sensitivity Study T/M Original Rev. 4A Sensitivity Case Notes Unavail.

Notes 1.61E-3 Sheet "X77, Y47 Hours" Note that there is a large increase in the planned unavailability resulting in a 122% increase when compared to the prior analysis.

1.58E-03 Sheet "X77, Y47 Hours" 3.15E-3 There was no data provided for this system. Assume 005 time is constant over time, so adjust by ratio of new exposure time to exposure time from last update (105192/52608).

1.78E-2 Therewas no data provided for t_his system. 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 Page 7'} of 132 Event Name L62-INV-MA-1Y80 l

Description 125 V DC/120 V AC INVERTER 1Y80 UNAVAILABLE FOR MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06-9/1/06-

-8/31/18 8/31/18 Unavail.

85.92 88618.01 9.70E-4 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes A CR search was There was no data provided performed to find any for this system. Assume occurrences of OOS time is constant over 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 Page 80 of 132 Event Name L62-INV-MA-1Y82 Description 125 V DC/120 V AC INVERTER 1Y82 UNAVAILABLE FOR MAINTENANCE OOS Hours 9/1/06-8/31/18 85.92 Exp. Hours 9/1/06-T/M 8/31/18 Unavail.

88618.01 9.70E-4 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes A CR search was There was no data provided performed to find any for this system. Assume occurrences of OOS time is constant over 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.

E NTGGGX083-RPT-001 Page 81 of 132

Event Name L62-INV-MA-1Y87 Description 125 V DC/120 V AC INVERTER 1 Y87 UNAVAILABLE FOR MAINTENANCE 005 Hours Exp. Hours T/M 9/1/06-9/1/06-Unavail.

8/31/18 8/31/18 85.92 88618.01 9.70E-4 Data Sensitivity Study Original Rev. 4A Notes Sensitivity Case Notes A CR search was There was no data provided performed to find any for this system. Assume occurrences of OOS time is constant over 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 Page 82 of 132 Event Name L62-INV-MA-1Y88 Description 125 V DC/120 V AC INVERTER 1Y88 UNAVAILABLE FOR MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06-9/1/06-Unavail.

8/31/18 8/31/18 85.92 88618.01 9.70E-4

\\

Data Sensitivity Study Original Rev. 4A Notes Sensitivity Case Notes A CR search was There was no data provided performed to fi._nd any for this system. Assume occurrences of OOS time is constant over 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.

E NTGGGX083-RPT-001 Page 83 of 132 Event Name L62-INV-MA-1 Y95 Description 125 V DC/120 V AC INVERTER 1Y95 UNAVAILABLE FOR MAINTENANCE 005 Hours 9/1/06-8/31/18 85.92 Exp. Hours T/M 9/1/06-8/31/18 Unavail.

88618.01 9.70E-4 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes A CR search was There was no data provided performed to find any for this system. Assume occurrences of OOS time is constant over 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.

E NTG GGX083-RPT-001 Page 84 of 132 Event Name L62-INV-MA-1 Y96 Description 125 V DC/120 V AC INVERTER 1 Y96 UNAVAILABLE FOR MAINTENANCE 005 Hours Exp. Hours T/M 9/1/06-9/1/06-8/31/18 8/31/18 Unavail.

85.92 88618.01 9.70E-4 Data Sensitivity Study

. Original Rev. 4A Sensitivity Case Notes Notes A CR search was There was no data provided performed to find any for this system. Assume occurrences of 005 time is constant over 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 Page 85 of 132 Event Name L62-INV-MA-1 Y99

\\_

Description 125 V DC/120 V AC INVERTER 1Y99 UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06-9/1/06-8/31/18 8/31/18 Unavail.

85.92 88618.01 9.70E-4 Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes A CR search was There was no data provided performed to find any for this system. Assume occurrences of OOS time is constant over 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 Page 86 of 132 Event Name E61-ANA-MA-DIV1 E61-ANA-MA-DIV2 Description TRAIN A HYDROGEN ANALYZERS UNAVAILABLE DUE TO MAINTENANCE TRAIN B HYDROGEN ANALYZERS UNAVAILABLE DUE TO MAINTENANCE OOS Hours Exp. Hours T/M 9/1/06-9/1/06-Unavail.

8/31/18 8/31/18 2304.00 105192.00 2.19E-2 2304.00 105192.00 2.19E-2 Data Sensitivity Study Original Rev. 4A Notes Sensitivity Case Notes Assume 8 tests/yr., 24 There was no data provided hrs. per test, based on for this system. Assume testing procedure and same 8 tests/yr., 24 hrs;per engineering estimate test as prior assumption of average duration using 12 years.

Assume 8 tests/yr., 24 There was no data provided hrs. per test, based on for this system. Assume testing procedure and same 8 tests/yr., 24 hrs. per engineering estimate test as prior assumption of average duration using 12 years.

E NTGGGX083-RPT-001 Page 87 of 132 Event Name E61-IGN-MA-DIV1 Description DIV I HYDROGEN IGNITERS UNAVAILABLE DUE TO MAINTENANCE

~

OOS Hours 9/1/06 -

8/31/18 24.00 Exp. Hours T/M 9/1/06-8/31/18 Unavail.

105192.00 2.28E-4**

Data Sensitivity Study Original Rev. 4A Sensitivity Case Notes Notes The Hydrogen igniters There was no data provided are tested four times for this system. Assume per year. According same as prior assumption 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).

E NTGGGX083-RPT-001 Page 88 of 132 Event Name E61-IGN-MA-DIV2 Description DIV II HYDROGEN IGNITERS UNAVAILABLE DUE TO MAINTENANCE 005 Hours Exp. Hours T/M 9/1/06-9/1/06-Unavail.

8/31/18 8/31/18 24.00 105192.00 2.28E-4

(

Data Sensitivity Study Original Rev. 4A Notes Sensitivity Case Notes The Hydrogen igniters There was no data. provided are tested four times for this system. Assume per year. According same as prior assumption 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 Page 89 of 132 Appendix D - Flag File UA.txt Data Sensitivity Study

ENTGGGX083-RPT-001 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 Data Sensitivity Study

ENTGGGX083-RPT-001 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 Data Sensitivity Study

ENTGGGX083-RPT-001 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 Data Sensitivity Study

ENTGGGX083-RPT-001 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 Data Sensitivity Study

E NTGGGX083-RPT-001 Page 94 of 132 Appendix E - CR Functional Failure Review (September 1, 2012 -August 31, 2018)

Data Sensitivity Study

ENTGGGX083-RPT-001 Page 95 of 132 Condition Component Report CR-GGN-1B21F002 2016-1065 CR-GGN-1821F113 2013-00332 CR-GGN-1B21HF103A 2014-2264 CR-GGN-1833D003A 2013-06764 CR-GGN-1B33K143A 2015-05760 CR-GGN-1C41F0048 2015-4832 CR-GGN-lC51K601A 2013-00085 CR-GGN-1C61N001B 2014-7495 CR-GGN-1C61R001A 2014-04511 CR-GGN-1C71N652D 2013-00757 CR-GGN-1C71N652D 2013-00965 CR-GGN-1D17P024/26 2015-638 Event Date 20-Feb-16 15-Jan-13 2-Mar-14 30-0ct-13 5-0ct-15 22-Aug-15 5-Jan-13 4-Nov-14 5-Jun-14 31-Jan-13 7-Feb-13 2-Feb-15 Data Sens_itivity Study PRA Data PRA Impact Associated BE or Disposition BE Description (if applicable)

Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability C41-EPV-CC-F004B NORMALLY CLOSED EXPLOSIVE EPVCC VALVE C41-F004B FAILS TO OPEN System not modeled in PRA or EOOS No impact on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability

~

Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability System not modeled in PRA or EOOS No impact on reliability

ENTGGGX083-RPT-001 Page 96 of 132 Condition Component Report CR-GGN-1E21AK108 2014-01696 CR-GGN-152-1705 2014-873 CR-GGN-1E30N003B/D 2015-1429 CR-GGN-1E30N003B/D 2015-1429 CR-GGN-1E51F063 2013-07720 CR-GGN-1E51F064 2015-1532 CR-GGN-1E51F064 2015-1677 CR-GGN-1E51K603 2014-00146 CR-GGN-1E51K603 2014-7810 CR-GGN-1E61J002B 2013-03132 CR-GGN-1G33C001A/B 2014-6799 CR-GGN-1G33C001A/B 2015-1823 CR-GGN-1G33C001A/B 2016-607 Event Date 21-Feb-14 9-Feb-14 8-Mar-15 8-Mar-15 17-Dec-13 12-Mar-15 20-Mar-15 9-Jan-14 18-Nov-14 8-May-13 2-0ct-14 26-Mar-15 31-Jan-16 Data Sensitivity Study PRA Data PRA Impact Associated BE or Disposition BE Description {if applicable)

Component not modeled in PRA or No impact EOOS on reliability E22-CBR-00-1705 NORMALLY OPEN CIRCUIT BREAKER CBROO 152-1705 FAILS TO CLOSE E30-ASL-DN-N003B SUPP POOL LEVEL SENS/TRANS E30-ASLDN LT-N003B FAILS TO FUNCTION E30-ASL-DN-N003D SUPP POOL LEVEL SENS/TRANS E30-ASLDN LT-N003D FAILS TO FUNCTION ES l-MOV-OC-F063 NORMALLY OPEN MOTOR DRIVEN MOVOC VALVE E51F063 FAILS CLOSED ES l-MOV-OC-F064 NORMALLY OPEN MOTOR DRIVEN MOVOC VALVE E51F064 FAILS CLOSED E51-MOV-OC-F064 NORMALLY OPEN MOTOR D~IVEN MOVOC VALVE E51F064 FAILS CLOSED E51-TDS-FS-C001-R RCIC TURBINE-DRIVEN PUMP FAILS TDS FS TO START E51-TDS-FS-C001-R RCIC TURBINE-DRIVEN PUMP FAILS TDS-FS TO START E61-ASP-DN-J002B TRAIN B CNTMNT HYDROGEN ASP DN ANALYZER FAILS TO FUNCTION Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability

ENTGGGX083-RPT-001 Page 97 of 132 Condition Component Report CR-GGN- \\

1G33F033 2013-4963 CR-GGN-1G33K600 2013-02899 CR-GGN-1M41F008 2015-4977 CR-GGN-1M71F592A 2014-4594 CR-GGN-1821F019 2016-1760 CR-GGN-1B21F032A 2014-01667 CR-GGN-1B21F032B 2016-1308 CR-GGN-1E51F040 2013-00689 CR-GGN-1P52F122 2015-3676 CR-GGN-1P71F149 2014-01597 CR-GGN-Nll pipe 2014-2824 CR-GGN-1N21C001B 2012-12487 CR-GGN-1N30N011B 2013-04943 Event Date 31-Jul-13 28-Apr-13 28-Aug-15 9-Jun-14 3-Mar-16 21-Feb-14 24-Feb-16 29-Jan-13 24-Jun-15 20-Feb-14 17-Mar-14 20-Nov-12

. 30-Jul-13 Data Sensitivity Study PRA Data PRA Impact Associated BE or Disposition BE Description {if applicable)

Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact I

EOOS on reliability System not modeled in PRA, No impact component not modeled in EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability B21-CKV-OO-F032A NORMALLY OPEN CHECK VALVE CKVOO B21-F032A FAILS TO CLOSE B21-CKV-OO-F032B NORMALLY OPEN CHECK VALVE CKVOO B21-F032B FAILS TO CLOSE ES 1-CKV-CC-F040 RCIC TURBINE EXHAUST LINE CHECK CKVOO VALVE F040 FAILS TO OPEN System not modeled in PRA or EOOS No impact on reliability Component not modeled in PRA or No impact EOOS on reliability Pipe failure not included in PRA data No impact on reliability N21-TDP-FR-C001B-F MAIN FEEDWATER TURBINE TDP FR DRIVEN PUMP N21-C001B FAILS TO RUN System not modeled in PRA or EOOS No impact on reliability

ENTGGGX083-RPT-001 Page 98 of 132 Condition Component Report CR-GGN-1N32D038 2013-6384 CR-GGN-1N41M701A 2012-13290 CR-GGN-1N41M701A 2013-00083 CR-GGN-1N41M705 2013-00319 CR-GGN-1N41M791 2014-3131 CR-GGN-NSl TVR 2014-3043 CR-GGN-1N71C001A 2013-07211 CR-GGN-1P41R700A 2014-0051 CR-GGN-52-170124 2013-7426 CR-GGN-SP41F074A 2013-07656 GGCR-2012-lPSlCOOlA 11043 CR-GGN-1P51C001A 2013-5153 CR-GGN-1P51C001A 2013-06508 Event Date 9-0ct-13 29-Dec-12 5-Jan-13 14-Jan-13 29-Mar-14 26-Mar-14 21-Nov-13 5-Jan-14 4-Dec-13 14-Dec-13 25-Sep-12 8-Aug-13 15-0ct-13 Data Sensitivity Study PRA Data PRA Impact Associated BE or Disposition BE Description (if applicable)

Component not modeled in PRA or No impact EOOS on reliability System not modeled in PRA or EOOS No impact on reliability System not modeled in PRA or EOOS No impact on reliability System not modeled in PRA or EOOS No impact on reliability System not modeled in PRA or EOOS No impact on_ reliability System not modeled in PRA or EOOS No impact on reliability N71-MDP-FR-C001A MOTOR DRIVEN PUMP N71-C001A MDP FR FAILS TO RUN Component not modeled in PRA or No impact EOOS on reliability P41-MDS-Fl-C002C-S STANDBY MOTOR DRIVEN PUMP MDS-Fl P41-C002 FAILS TO RUN IN FIRST HOUR Component not modeled in PRA or No impact EOOS on reliability PSl-MDC-FR-COOlA-P PS PLANT AIR COMPRESSOR COOlA MDC FR FAILS TO CONTINUE RUNNING PSl-MDC-FR-COOlA-P PS PLANT AIR COMPRESSOR COOlA MDC FR FAILS TO CONTINUE RUNNING P51-MDC-FR-C001A-P PS PLANT AIR COMPRESSOR COOlA MDC FR FAILS TO CONTINUE RUNNING

ENTGGGX083-RPT-001 Page 99 of 132 Condition Component Report CR-GGN-1P51C001A 2013-7038

'~

CR-GGN-1P51C001A 2014-6114 CR-GGN-1P51C001A 2015-1582 CR-GGN-1P51C001B 2014-4274

-GGCR-2012-1P51C001C 10982 CR-GGN-1P51C001C 2013-5209 CR-GGN-1P51C001C 2015-4584 CR-GGN-1P75E001A 2013-05899 CR-GGN-1P75E001A 2015-6831 CR-GGN-1P75E001B 2013-03423 CR-GGN-1P75R608B 2013-07040 CR-GGN-DG12-151GD 2014-7826 CR-GGN-1P81N606 2015-03985 Event'Date 13-Nov-13 26-Aug-14 16-Mar-15 23-May-14 23-Sep-12 11-Aug-13 10-Aug-15 17-Sep-13 21-Nov-15 21-May-13 13-Nov-13 19-Nov-14 13-Jul-15

Data Sensitivity Study PRA Data PRA Impact Associated BE or Disposition BE Description {if applicable)

P51-MDC-FR-C001A-P PS PLANT AIR COMPRESSOR COOlA MDC FR FAILS TO CONTINUE RUNNING P51-MDC-FR-C001A-P PS PLANT AIR COMPRESSOR COOlA MDC FR FAILS TO CONTINUE RUNNING P51-M DC-FR-C001A-P PS PLANT AIR COMPRESSOR C001A MDC FR FAILS TO CONTINUE RUNNING P51-MDC-FR-C001B-P AIR COMPRESSOR C001B FAILS TO MDCFS START P51-MDC-FR-C001C-P PS PLANT AIR COMPRESSOR COOlC MDC FR FAILS TO CONTINUE RUNNING P51-MDC-FR-C001C-P PS PLANT AIR COMPRESSOR C001C MDC FR FAILS TO CONTINUE RUNNING P51-MDC-FR-C001C-P AIR COMPRESSOR C001C FAILS TO MDCFS START P75-DGN-Fl-DG11 DG11 FAILS TO RUN DURING 1ST DGN Fl HOUR OF OPERATION P75-DGN-F1-DG11 DG11 FAILS TO RUN DURING lST DGN Fl HOUR OF OPERATION P75-DGN-F1-DG12 DG12 FAILS TO RUN DURING lST DGN Fl HOUR OF OPERATION Component not modeled in PRA -,

No impact failure would not prevent DG 12 from on reliability continued operation P75-DG N-FS-DG 12 DG12 FAILS TO START DGN FS Component not modeled in PRA or No impact EOOS -

on reliability

E NTGGGX083-RPT-001 Page 100 of 132 Condition Component

_ Report CR-GGN-1R14S001A 2013-4553 CR-GGN-1R14S001A 2013-6263 CR-GGN-1R14S001A 2014-3733 CR-GGN-1R14S001B 2015-0801 GGCR-2012-AUX BLDG 11352 CR-GGN-Aux Bldg Penet 2013-02812 CR-GGN-no 2013-01104 CR-GGN-no AUX BLDG 2012-12152 CR-GGN-no Aux Building 2015-4423 CR-GGN-no Auxiliary 2014-4733 Building CR-GGN-no Roof 2013-7345 CR-GGN-T 48 SBGT System 2015-5661 CR-GGN-1T46B002A 2014-05306 Data Sensitivity Study PRA-Data Event Date

PRA Impact Associated BE or Disposition BE Description (if applicable) 12-Jul-13 System not modeled in PRA or EOOS No impact on reliability 3-0ct-13 System not modeled in PRA or EOOS No impact on reliability 27-Apr-14 System not modeled in PRA or EOOS No impact on reliability

, 7-Feb-15 System not modeled in PRA or EOOS No impact on reliability 5-0ct-12 System not modeled in PRA or EOOS No impact on reliability 24-Apr-13 System not modeled in PRA or EOOS No impact on reliability 11-Feb-13 System not modeled in PRA or EOOS No impact on reliability 5-Nov-12 System not modeled in PRA or EOOS No impact on reliability 2-Aug-15 System not modeled in PRA or EOOS No impact on reliability 17-Jun-14 System not modeled in PRA or EOOS No impact on reliability 30-Nov-13 System not modeled in PRA or EOOS No impact on reliability 1-0ct-15 System not modeled in PRA or EOOS No impact on reliability 17-Jul-14 System not modeled in PRA or EOOS No impact on reliability

E NTGGGX083-RPT-001 Page 101 of 132 Condition Report Component CR-GGN-1T4680048 2014-06116 CR-GGN-1T4680058 2015-02614 CR-GGN-52-154145 2015-01938 CR-GGN-52-151130 2016-2386 CR-GGN-X70 Roof 2013-6597 CR-GGN-X70 Roof 2013-7802 CR-GGN-1Y47F002 2014-8155 CR-GGN-1Y47-F002A 2015-0342 CR-GGN-1Y47F002B/N004B 2015-00745 CR-GGN-1Y47Y001A 2013-02932 CR-GGN-Various 2014-08441 CR-GGN-SZ51B002B 2014-7413 CR-GGN-SZ518002B 2015-1728 Event Date 26-Aug-14 2-May-15 1-Apr-15 15-Mar-16 21-0ct-13 20-Dec-13 8-Dec-14 18-Jan-15 5-Feb-15 29-Apr-13 27-Dec-14 31-0ct-14 24-Mar-15 Data Sensitivity Study PRA Data PRA*lmpact Associated BE or Disposition BE Description (if applicable)

System not mode_led in PRA or EOOS No impact on reliability System not modeled in PRA or EOOS No impact on reliability System not modeled in P~A or EOOS Also breaker not mapped in EOOS No impact on reliability Component not modeled in PRA or No impact EOOS on reliability System not modeled in PRA or EOOS No impact on reliability System not modeled in PRA or EOOS No impact on reliability Y47-MOD-CC-F02AA MOD 1Y47-F002A FAILS TO OPEN MOD CC Y47-MOD-CC-F02AA MOD 1Y47-F002A FAILS TO OPEN MOD CC Y47-MOD-CC-F02BB MOD 1Y47-F0028 FAILS TO OPEN MOD CC Y47-MOD-CC-F02BB MOD 1Y47-F002B FAILS TO OPEN MOD CC Y47-MOD-CC-F02AA MOD 1Y47-F002A FAILS TO OPEN MOD CC System not modeled in PRA or EOOS No impact on reliability System not modeled in PRA or EOOS No impact on reliability

E NTGGGX083-RPT-001 Page 102 of 132 Condition Component Report CR-GGN-SZ51B002B 2015-2037 CR-GGN-1Z778001A 2015-01927 CR-GGN-2Z77C001A 2014-05317 CR-GGN-52-164101 2013-6274 CR-GGN-1N41M703 (XFM R 2016-2950 Diff Phase B}

CR-GGN-1C71N0018, 2016-2950 1C71N0019 (TCV Fast Closure Chs B&C)

CR-GGN-1E31N684A 2016-3063 CR-GGN-2016-3063 CR-GGN-1833N150B 2016-3079 CR-GGN-1B33F060B(RX 2016-3079 Recirc Loop B FCV)

CR-GGN-lCllAOOlBM 2016-3238 CR-GGN-1P60F009 2016-3551 Event Date 6-Apr-15 1-Apr-15 17-Jul-14 3-0ct-13 29-Mar-16 29-Mar-16 1-Apr-16 1-Apr-16 2-Apr-16 2-Apr-16 11-Apr-16 22-Apr-16 Data Sensitivity Study PRA Data PRA Impact Associated BE or Disposition BE Description (if applicable)

System not modeled in PRA or EOOS No impact on reliability Z77-FNS-FR-B001A-S UNIT 1 TRAIN A SUPPLY SIDE FAN FNS FR 1Z77-8001A FAILS TO RUN Z77-FNS-Fl-2C01A-S UNIT 2 TRAIN A EXHAUST SIDE FAN FNS FR 2277-COOlA FAILS TO RUN Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reli.ability Component not modeled in PRA or No impact EOOS on reliability

/

Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability

ENTGGGX083-RPT-001 Page 103 of 132 Condition Component Report CR-GGN-1G36AF002 2016-4192 CR-GGN-1P75L605B (D2 2016-04410 EDG Lockout Relay) 1P75E001B (D2EDG)

CR-GGN-1N32F515C (Main 2016-4766 Stop Valve)

CR-GGN-1N31D001 2016-4998 CR-GGN-1E12F0188 2016-5087 CR-GGN-2RJ5S121 (Service 2016-5153 XFMR #21) 2R11S123 (BOP XFMR #23)

CR-GGN-1Y47F001A 2016-05211 CR-GGN-152-1705 2016-5329 CR-GGN-1E12F048A 2016-6798 CR-GGN-1B21F002 2016-6887 CR-GGN-1G36F101 2016-06999 Event Date 22-May-16 2-Jun-16 17-Jun-16 25-Jun-16 29-Jun-16 30-Jun-16 3-Jul-16 8-Jul-16 4-Sep-16 9-Sep-16 13-Sep-16 Data Sensitivity Study PRA Data PRA Impact Associated BE or Disposition BE Description {if applicable)

Component not modeled in PRA or No impact EOOS on reliability P75-DGN-FS-DG12 DG12 FAILS TO START DGN FS Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability External valve leak not modeled No impact on reliability R15-PTR-LP-SVC21 SERVICE TRANSFORMER 21 PTR LP HARDWARE FAILURE Y47-MOD-CC-F01AA MOD 1Y47-F001A FAILS TO OPEN MOD CC E22-CBR-CC-1704 NORMALLY CLOSED CIRCUIT CBR CC BREAKER 152-1704 FAILS TO OPEN No FF, valve was just out of spec.,

No impact and needed throttling adj.

on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability

ENTGGGX083-RPT-001 Page 104 of 132 Condition Report Component CR-GGN-1E22C003(HPCS 2017-916 Jockey Pump)

CR-GGN-1N19C002B 2017-1486 CR-GGN-1B21CKOOSA 2017-1939 CR-GGN-1Nl9C002C 2017-1956 CR-GGN-1T48R600A (SGTS 2017-2968 Filter train A Flow Recorder)

CR-GGN-1P51F256A (Dryer 2017-3025 A Left Tower Purge Flow Valve)

CR-GGN-1P41N016A ( SSW 2017-3084 Loop A Discharge Flow Xmittter)

CR-GGN-1N37F100A 2017-3333 (Water Injection Valve)

CR-GGN-1T48R602B 2017-3481 (Enclosure Building Outside DP Recorder)

Event Date 27-Jan-17 10-Feb-17 23-Feb-17 24-Feb-17 24-Mar-17 26-Mar-17 28-Mar-17 4-Apr-17 7-Apr-17 Data Sensitivity Study PRA Data PRA Impact Associated BE or Disposition BE Description (if applicable)

Component not modeled in PRA or No impact EOOS on reliability N19-MDP-FR-C002B CONDENSATE BOOSTER MOTOR MDP FR DRIVEN PUMP N19-C002B FAILS TO RUN 821-TIM-DD-KSA DIVISION 1 (A) 105 SEC TIMER 821-TIMDO KSA FAILS N19-MOP-FR-C002C CONDENSATE BOOSTER MOTOR MOP FR DRIVEN PUMP N19-C002C FAILS TO RUN Component not modeled in PRA or No impact EOOS on reliability No PRA event to map spurious open AOVOC to. Assume valve is AOV Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability I

E NTG GGX083-RPT-001 Page 105 of 132 Condition Report Component CR-GGN-1B21KOOSA 2017-5374 CR-GGN-1P51C0018 2017-5917 CR-GGN-Door OC 516 2017-6705 CR-GGN-1N21A001B 2017-06842 (Control Fluid Reservoir) 1N21F5198 (RFPT B CV Positioner 7

Assembly)

CR-GGN-1T48F005 (Stm 2017-6881 Tunnel SGTS Flow Control Valve)

CR-GGN-1Y47F003B 2017-07635 (1Y47C001B Inlet Damper)

CR-GGN-1E12C002A, 2017-8434 1E12F006A CR-GGN-1C61R001A (SSW 2017-8489 A System Flow (RSM) indicator)

CR-GGN-1M23Y002N (208' 2017-08848 Airlock Outer Door)

Event Date 26-May-17 13-Jun-17 10-Jul-17 13-Jul-17 14-Jul-17 4-Aug-17 27-Aug-17 28-Aug-17 7-Sep-17

/

Data Sensitivity Study PRA Data PRA Impact Associated BE or Disposition BE Description (if applicable) 821-TIM-DD-KSA DIVISION 1 (A) 105 SEC TIMER 821-TIMDD K5A FAILS PSl-MDC-FR-COOlB-P PS PLANT AIR COMPRESSOR COOlB MDC FR FAILS TO CONTINUE RUNNING Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Y47-MOD-CC-F01BB MOD 1Y47-F001B FAILS TO OPEN MOD CC E12-MDS-FR-C002A MOTOR-DRIVEN PUMP C002A FAILS MDSFR TO CONTINUE RUNNING Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability

ENTGGGX083-RPT-001 Page 106 of 132 Condition Component Report CR-GGN-1E22S001 {HPCS 2017-9058 DG)

CR-GGN-1017P024 {SGTR B 2017-10042 Vent Normal Range Panel),

1C91K106 (Horizon Supervisory Sys)

CR-GGN-1E61F003B 2017-10756 (Drywell Purge Supply)

CR-GGN-1P60F009 (SPCU 2017-10797 Return from CNDS PC Filters)

CR-GGN-1833C001B(Rx 11427 Recirculation pump B)

CR-GNN~

1C11A001FH 2017-11739 (Accumulator for HCU 24-33)

CR-GGN-1P60F009 (SPCU 2017-11786 Return from CNDS PC Filters)

CR-GGN-1E31AK002A & B 2017-12314 (Agastat Relays Skeletal Entry)

Event Date 12-Sep-17 5-0ct-17 26-0ct-17 27-0ct-17 15-Nov-17 25-Nov-17 27-Nov-17 12-Dec-17 Data Sensitivity Study PRA Data PRA Impact Associated BE or Disposition BE Description {if applicable)

L11-BAT-LP-1C3 DIV Ill BATIERY 1C3 FAILS (NO BAT LP OUTPUT /POWER)

Component not modeled in PRA or No impact EOOS on reliability E61-MOV-OO-F003B NORMALLY OPEN MOTOR DRIVEN MOVOO VALVE F003B FAILS TO CLOSE Component not modeled in PRA or No impact EOOS on reliability No PRA failure, only fail to trip is No impact relevant to PR-A on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability

ENTGGGX083-RPT-001 Page 107 of 132 Condition Component Report CR-GGN-lESlCOOl (RCIC 2017-12299 Pump), 152-1704 (ESF Trans #12 Source Bus 17 AC)

CR-GGN-1P41N018B (SSW 2018-00200 Clg Tower B Return Flow Xmitter)

CR-GGN-1N11F037A, 2018-00218 1N11F039A, 1N33F080A & B, 1N33F178 CR-GNN-lCllAOOlHP 2018-00303 (Accumulator for HCU 32-57)

CR-GGN-1C91K010P(P 2018-564 MUX VME Chassis)

- CR-GGN-SDl 7L654 (SBGT 2018-591 A/B Hi Rad/ EFFFL Rad Mon)

CR-GGN-1017N205E (SGTS 2018-643 B Vent Stack Flow Rate)

CR-GGN-SD17L660 (EFFL 2018-717 Rad Mon Trouble)

CR-GGN-1H13P825JC05 2018-00918 Data Sensitivity Study PRA Data Event Date PRA Impact Associated BE or Disposition BE Description (if applicable) 12-Dec-17 E22-CBR-CO-l 704 BREAKER 152-1704 FAILS OPEN CBR CO 7-Jan-18 Component not modeled in PRA or No impact EOOS on reliability 8-Jan-18 Component not modeled in PRA or No impact EOOS on reliability 10-Jan-18 Component not modeled in PRA or No impact EOOS on reliability 20-Jan-18 Component not modeled in PRA or No impact EOOS on reliability 22-Jan-18 Component not modeled in PRA or No impact EOOS on reliability 23-Jan-18 Component not modeled in PRA or No impact EOOS on reliability 24-Jan-18 Component not modeled in PRA or No impact EOOS on reliability 30-Jan-18 Component not modeled in PRA or No impact EOOS on reliability

ENTGGGX083~RPT-001 Page 108 of 132 Condition Component Report CR-GGN-SD17L654(SBGT 2018-1307 A/B Hi Rad/ EFFFL Rad Mon)

CR-GGN-1P818003B(HPCS 2018-01512 DG Jacket Water Heater),

1P81N044B (Engine B JW Heater Temp Sw)

CR-GGN-525180028 2018-1629 (Control Room AC)

CR-GGN-1D17P025 (SGTS B 2018-1764 Vent Noble Gas Monitor)

CR-GGN-1017P027 (SGTS A 2018-1767 Vent Noble Gas Pallet)

CR-GGN-1D17P025 2018-2410 CR-GGN-1Tl01A319A 2018-2962 (Outer Aux.

Railroad Bay Door)

CR-GGN-SGTS A/B SPI NG 2018-3222 CR-GGN-1D17P025 (SGTS B 2018-05198 Vent Noble Gas Monitor)

Data Sensitivity Study PRA Data Event Date PRA Impact Associated BE or Disposition BE Description (if applicable) 12-Feb-18 Component not modeled in PRA or No impact EOOS on reliability 17-Feb-18 Component not modeled in PRA or No impact EOOS on reliability 21-Feb-18 Component not modeled in PRA or No impact EOOS on reliability 24-Feb-18 Component not modeled in PRA or No impact EOOS on reliability 24-Feb-18 Component not modeled in PRA or No imp~ct EOOS on reliability 15-Mar-18 Component not modeled in PRA or No impact EOOS on reliability 31-Mar-18 Component not modeled in PRA or No impact EOOS on reliability 6-Apr-18 Component not modeled in PRA or No impact EOOS on reliability

7-May-18 Component not modeled in PRA or No impact EOOS on reliability

ENTGGGX083-RPT-001 Page 109 of 132 Condition Component Report CR-GGN-1D17J115 2018-05889 CR-GGN-525180028 2018-06469

( Control Room AC)

CR-GGN-1C61R025 2018-7431 (Remote SD Sys Transf Panel Relay)

CR-GGN-15_2-1702 (HPCS 2018-7762 Pump 1E22C001)

CR-GGN-1T48K699B (SGTS 2018-8005 Instrument Power Supply)

CR-GGN-1833C001A (Rx 2018-8706 Recirc Pump A Motor)

CR-GGN-Dl 7L024 (SGTS B 2018-8958 EFFL Rad Mon Trouble)

-0 CR-GGN-1P41N018B (SSW 2018-9242 ClgTower B Return Flow Xmitter)

CR-GGN-SD17L654(SBGT 2018-9330 A/B Hi Rad/ EFFFL Rad Mon)

Data Sensitivity Study PRA Data Event Date PRA Impact Associated BE or Disposition BE Description {if applicable) 21-May-18 Component not modeled in PRA or No impact EOOS on reliability 3-Jun-18 Component not modefed in PRA or No impact EOOS on reliability 26-Jun-18 Component not modeled in PRA or No impact EOOS on reliability 5-Jul-18 E22-MDS-FS-C001 HPCS MOTOR DRIVEN PUMP COOl MOS FS FAILS TO START 12-Jul-18 Component not modeled in PRA or No impact EOOS on reliability

(

30-Jul-18 No PRA failure, only fail to trip is No impact relevant to PRA on reliability 4-Aug-18 Component not modeled in PRA or No impact EOOS on reliability 10-Aug-18 Component not modeled in PRA or No impact EOOS on reliability 13-Aug-18 Component not modeled in PRA or No impact EOOS on reliability

ENTGGGX083-RPT-001 Page 110 of 132 Condition Component Report CR-GGN-1D17N127 (Ctmt 2018-9436 Vent Axm NGP HR NG Rad Detect.)

eR-GGN-1N23F514B (FW 2018-HTR 68 Drn Valve) 9632/9635 CR-GGN-1E12F048A RHR 2018-9705 Hx A Bypass Valve)

Event Date 16-Aug-18 21-Aug-18 23-Aug-18 Data Sensitivity Study PRA Data PRA Impact Associated BE or Disposition BE Description {if applicable)

Component not modeled in PRA or No impact EOOS on reliability Component not modeled in PRA or No impact EOOS on reliability E12-MOV-OC-F048A MOTOR-OPERATED VALVE F048A MOVOC PLUGS

E NTGGGX083-RPT-001 Page 111 of 132 Appendix F - GGNS Functional Failures (September 1, 2006 -August 31, 2018)

Data Sensitivity Study

ENTGGGX083-RPT-001 Page 112 of 132 Type Code Description AOVCC Normally Closed Air Operated Valve F034 Fails to Open AOVOC Air-Operated Valve Fails to Remain Open AOVOC Normally Open Air Operated Valve F289 Fails Closed AOVOC Air-Operated Valve F011 Fails to Remain Open Due to Hardware Failure ASLDN SUPP POOL LEVEL SENS/TRANS E30-LT-N003B FAILS,TO FUNCTION ASLDN SUPP POOL LEVEL SENS/TRANS E30-LT-N003D FAILS TO FUNCTION ASP DN TRAIN B CNTMNT HYDROGEN ANALYZER FAILS TO FUNCTION BAT LP DIV Ill BATTERY 1C3 FAILS (NO OUTPUT/POWER)

CBR CC Circuit Breaker Failure CBR CC NORMALLY CLOSED CIRCUIT BREAKER 152-1704 FAILS TO OPEN CBRCO BREAKER 152-1704 FAILS OPEN CBROO NORMALLY OPEN CIRCUIT BREAKER 152-1705 FAILS TO CLOSE CKVOO NORMALLY OPEN CHECK VALVE B21-F032A FAILS TffCLOSE CKVOO NORMALLY OPEN CHECK VALVE B21-F032B FAILS TO CLOSE CKVOO RCIC TURBINE EXHAUST LINE CHECK VALVE F040 FAILS TO OPEN DGN Fl DGll FAILS TO RUN DURING lST HOUR OF OPERATION DGN Fl DGll FAILS TO RUN DURING lST HOUR OF OPERATION DGN Fl DG12 FAILS TO RUN DURING lST HOUR OF OPERATION DGN Fl Diesel Generator Fails to Run During First Hour of Operation DGN FS DG12 FAILS TO START DGN FS DG12 FAILS TO START EPVCC NORMALLY CLOSED EXPLOSIVE VALVE C41-F004B FAILS TO OPEN FNS FR UNIT 2 TRAIN A EXHAUST SIDE FAN 2277-COOlA FAILS TO RUN FNS FR UNfT 1 TRAIN A SUPPLY SIDE FAN 1277-BOOlA FAILS TO RUN FNS FS Fan Fails to Start MCSFS Standby Air Compressor 1P47C002A Fails to Start Data Sensitivity Study Component Plant Documentation M41-AOV-CC-F034 CR-GGN-2012-09747 1P51F256A CR-GGN-2017-3025 P43-AOV-OC-VF289 CR-GGN-2009-04 781 P44-AOV-OC-F011 CR-GGN-2007-05463 E30-ASL-D N-N003 B CR-GGN-2015-1429 E30-ASL-DN-N003D CR-GGN-2015-1429 E61-ASP-DN-J002B CR-GGN-2013-03132 L11-BAT-LP-1C3 CR-GGN-2017-9058

1EQ18AG CR-GGN-2011-08539 E 22-CB R-CC-1704 CR-GGN-2016-5329 E22-CBR-C0-1704 CR-GGN-2017-12299 E22-CBR-00-1705 CR-GGN-2014-873 B21-CKV-OO-F032A CR-GG N-2014-01667 B21-CKV-OO-F032B CR-GGN-2016-1308 ES 1-CKV-CC-F040 CR-GGN-2013-00689 P75-DGN-Fl-DG11 CR-GGN-2013-05899 P75-DGN-F1-DG11 CR-GGN-2015-6831 P75-DGN-Fl-DG12 CR-GGN-2013-03423 P75E001A GGCR-2007-00378 P75-DG N-FS-DG 12 CR-GGN-2014-7826 P75-DG N-FS-DG 12 CR-GGN-2016-04410 C41-EPV-CC-F004B CR-GGN-2015-4832 Z77-FNS-Fl-2C01A-S CR-GGN-2014-05317 Z77-FNS-FR-B001A-S CR-GGN-2015-01927 1Z77C001B GGCR-2010-01870 P4 7-MCS-FS-C002A CR-GGN-2012-09653

ENTGGGX083-RPT-001 Page 113 of 132 Type Code Description MDC FR Air Compressor C001A Fails to Continue Running MDC FR PS PLANT AIR COMPRESSOR C001A FAILS TO CONTINUE RUNNING MDC FR PS PLANT AIR COMPRESSOR C001A FAILS TO CONTINUE RUNNING

/

MDC FR PS PLANT AIR COMPRESSOR C001A FAILS TO CONTINUE RUNNING MDC FR PS PLANT AIR COMPRESSOR C001A FAILS TO CONTINUE RUNNING MDC FR PS PLANT AIR COMPRESSOR C001A FAILS TO CONTINUE RUNNING MDC FR PS PLANT AIR COMPRESSOR COOlA FAILS TO CONTINUE RUNNING MDC FR Air Compressor COOlB Fails to Continue Running MDC FR Air Compressor COOlB Fails to Continue Running MDC FR PS PLANT AIR COMPRESSOR C001B FAILS TO CONTINUE RUNNING MDC FR PS PLANT AIR COMPRESSOR COOlC FAILS TO CONTINUE RUNNING MDC FR PS PLANT AIR COMPRESSOR COOlC FAILS TO CONTINUE RUNNING MDCFS AIR COMPRESSOR COOlB FAILS TO START MDCFS AIR COMPRESSOR COOlC FAILS TO START MDP FR CONDENSATE BOOSTER MOTOR DRIVEN PUMP N19-C002B FAILS TO RUN MDP FR CONDENSATE BOOSTER MOTOR DRIVEN PUMP N19-C002C FAILS TO RUN MDP FR MOTOR DRIVEN PUMP N71-C001A FAILS TO RUN MDS FR MOTOR-DRIVEN PUMP C002A FAILS TO CONTINUE RUNNING MDS FS STANDBY MOTOR DRIVEN PUMP P41-C002 FAILS TO RUN IN FIRST HOUR MDS FS HPCS MOTOR DRIVEN PUMP COOl FAILS TO START MOD CC MOD 1 Y47-F001A FAILS TO OPEN MOD CC MOD 1Y47-F001B FAILS TO OPEN MOD CC MOD 1Y47-F002A FAILS TO OPEN MOD CC MOD 1Y47-F002A FAILS TO OPEN MOD CC MOD 1Y47-F002A FAILS TO OPEN MOD CC MOD 1Y47-F002B FAILS TO OPEN Data Sensitivity Study Component Plant Documentation P51-MDC-FR-C001A CR-GGN-2011-02091 P51-MDC-FR-C001A-P CR-GGN-2013-06508 P51-MDC-FR-C001A-P CR-GGN-2013-5153 P51-MDC-FR-C001A-P CR-GGN-2013-7038 P51-MDC-FR-C001A-P CR-GGN-2014-6114 P51-MDC-FR-C001A-P CR-GGN-2015-1582 P51-MDC-FR-C001A-P GGCR-2012-11043 P51-MDC-FR-C0018 CR-GGN-2010-08815 P51-MDC-FR-C001B CR-GGN-2012-00005 P51-MDC-FR-C001B-P CR-GGN-2017-5917 P51-MDC-FR-C001C-P CR-GGN-2013-5209 P51-MDC-FR-C001C-P GGCR-2012-10982 PSl-MDC-FR-COOlB-P CR-GGN-2014-4274 PSl-MDC-FR-COOlC-P CR-GGN-2015-4584 N 19-MDP-FR-C002B CR-GGN-2017-1486 N19-MDP-FR-C002C CR-GGN-2017-1956 N71-MDP-FR-C001A CR-GGN-2013-07211 E12-MDS-FR-C002A CR-GGN-2017-8434 52-170124 CR-GGN-2013-7426 E22-MDS-FS~C001 CR-GGN-2018-7762 Y47-MOD-CC-F01AA CR-GGN-2016-05211 Y 4 7-MOD-CC-FOlBB CR-GGN-2017-07635 Y47-MOD-CC-F02AA CR-GGN-2014-08441 Y47-MOD-CC-F02AA CR-GGN-2014-8155 Y 4 7-MOD-CC-F02AA CR-GGN-2015-0342 Y47-MOD-CC-F02BB CR-GGN-2013-02932

ENTGGGX083-RPT-001 Page 114 of 132 Type Code Description MOD CC MOD 1Y47-F002B FAILS TO OPEN MOVCC Minimum Flow Valve F012-C Fails to Open MOVOC MOTOR-OPERATED VALVE F048A PLUGS MOVOC NORMALLY OPEN MOTOR DRIVEN VALVE E51F063 FAILS CLOSED MOVOC NORMALLY OPEN MOTOR DRIVEN VALVE E51F064 FAILS CLOSED MOVOC NORMALLY OPEN MOTOR DRIVEN VALVE E51F064 FAILS CLOSED MOVOO NORMALLY OPEN MOTOR DRIVEN VALVE F003B FAILS TO CLOSE MOVOO SSW Recirc Valve F006B Fails to Close PTR LP SERVICE TRANSFORMER 21 HARDWARE FAILURE TDP FR MAIN FEEDWATER TURBINE DRIVEN PUMP N21-C001B FAILS TO RUN TDS FS RCIC TURBINE-DRIVEN PUMP FAILS TO START TDS FS RCIC TURBINE-DRIVEN PUMP FAILS TO START TIMDD DIVISION 1 (A) 105 SEC TIMER 821-KSA FAILS TIMDD DIVISION 1 (A) 105 SEC TIMER 821-KSA FAILS Data Sensitivity Study Component Plant Documentation Y47-MOD-CC-F02BB CR-GGN-2015-00745 E22-MOV-CC-F012 CR-GGN-2011-01911 E12-MOV-OC-F048A CR-GGN-2018-9705 E51-MOV-OC-F063 CR-GGN-2013-07720 E51-MOV-OC-F064 CR-GGN-2015-1532 E51-MOV-OC-F064 CR-GGN-2015-1677 E61-MOV-OO-F003B CR-GGN-2017-10756 P41-MOV-OO-F006B CR-GGN-2012-05598 R15-PTR-LP-SVC21 CR-GGN-2016-5153 N21-TDP-FR-C001B-F CR-GGN-2012-12487 E51-TDS-FS-C001-R CR-GGN-2014-00146 E51-TDS-FS-C001-R CR-GGN-2014-7810 821-TIM-DD-KSA CR-GGN-2017-1939 821-TIM-DD-KSA CR-GGN-2017-5374

E NTGGGX083-RPT-001 Page 115 of 132 Appendix G - Runtime and Demand Estimates (September 1, 2006-August 31, 2018)

Data Sensitivity Study

ENTGGGX083-RPT-001 Page 116 of 132 Type Description Code AOVCC Air-Operated Valve Fails to Open AOVOC Air-Operated Valve Transfers Closed ASLDN Level Transmitter Fails on Demand ASP DN Pressure Transmitter Fails on Demand BAT LP Battery Fails to Operate CBR CC Circuit Breaker Fails to Open CBRCO Circuit Breaker Fails to Remain Closed CBROO Circuit Breaker Fails to Close CKVOO Check Valve Fails to Close DGN Fl Diesel Generator Fails to Run During the First Hour DGN FS Diesel Generator Fails to Start

/

EPV CC Explosive Valve Fails to Open FNS FR Fan (Standby) Fails to Run After the First Hour FNS FS Fan (Standby) Fails to Start MCS FS Motor-Driven Air Compressor (Standby)

Fails to Start MDC FR P Motor-Driven Air Compressor Fails to Run Distribution B

G B

B G

B B

G B

B G

B B

G Data Sensitivity Study Demands

\\_

or Hours Notes on Update Method 86 Comp Dem and Exp - Sens.xlsx: Update AOV CC worksheet with new BE list and rx crit. time 4785372 Comp Dem and Exp - Sens.xlsx: Update AOV OC worksheet with new BE list and rx crit. time 1740 Comp Dem and Exp - Sens.xlsx: Created ASL ON worksheet with BE list assuming quarterly test 2144 Comp Dem and Exp - Sens.xlsx: Created ASP DN worksheet with BE list assuming quarterly test 630864 App c-1.xls time= 315432 hrs

2 - 630864 hours 96 Comp Dem and Exp - Sens.xlsx: Created CBR CC worksheet with BE list assuming outage test 15153679 Comp Dem and Exp - Sens.xlsx: Created CBR CO worksheet with new BE list and rx crit. time 116 Comp Dem and Exp - Sens.xlsx: Created CBR 00 worksheet with BE list assuming outage test N/A Not a single CKV 00 BE was risk significant in FPIE, so will not update.

2802 App c-1.xls: Assume same as number of starts for DGN FS 2802 App c-1.xls: Assume starts from 9/2006 - 8/2012 same as from 9/2012 - 8/2018 10 Comp Dem and Exp - Sens.xlsx: Update EPV CC worksheet with new BE list and rx crit. time App c-1.xls: Assume runtime from 9/2006 - 8/2012 same 958780 as from 9/2012 - 8/2018 11371 App c-1.xls: Assume starts from 9/2006 - 8/2012 same as from 9/2012 - 8/2018 445 Comp Dem and Exp - Sens.xlsx: Update MCS FS worksheet with new BE list and rx crit. time 94821 App c-1.xls: Assume 1 comp runs constantly with 2nd comp 7% of critical yr

ENTGGGX083-RPT-001 Page 117 of 132 Type Description Code MDC FS P Motor-Driven Air Compressor Fails to Start MDP FR Motor-Driven-Pump Fail to Run MDSFR Motor-Driven Pump (Standby) Fails to Run After the First Hour MDSFS Motor-Driven Pump (Standby) Fails to Start MOD CC Motor-Operated Damper Fails to Open MOVCC Motor-Operated Valve Fails to Open MOVOC Motor-Operated Valve Transfers Closed MOVOO Motor-Operated Valve Fails to Close PTR LP Transformer Fails to Function TDP FR Turbine Driven Pump Fail to Run TDS FS RCIC Turbine-Driven Pump (Standby) Fails to Start TIMDD Timer Fails to Operate Distribution B

G G

B B

B G

G B

G Data Sensitivity Study Demands or Hours Notes on Update Method App c-1.xls: Assume starts from 9/2006 - 8/2012 same as 451 from 9/2012 - 8/2018 3235768 App c-1.xls: Assume runtime from 9/2006 - 8/2012 same as from 9/2012 - 8/2018 20668 App c-1.xls: Assume runtime from 9/2006 - 8/2012 same as from 9/2012 - 8/2018 1677 App c-1.xls: Assume starts from 9/2006 - 8/2012 same as from 9/2012 - 8/2018 10507 App c-1.xls: Est. on Y47 & X77 Fan starts. Assume starts from 9/06 - 8/12 same as 9/12 - 8/16 3404 Comp Dem and Exp - Sens.xlsx: Update MOV CC worksheet with new BE list and rx crit. time 7266677 Comp Dem and Exp - Sens.xlsx: Update MOV CO worksheet with new BE list and rx crit. time 1634 Comp Dem and Exp - Sens.xlsx: Update MOV 00 worksheet with new BE list and rx crit. time -

3680044 App c-1.xls: Assume runtime from 9/2006 - 8/2012 same as from 9/2012 - 8/2018 201600 App c-1.xls: Assume runtime from 9/2006 - 8/2012 same as from 9/2012 - 8/2018 381 App c-1.xls: Assume startsfrom 9/2006 - 8/2012 same as from 9/2012 - 8/2018 974798 Comp Dem and Exp - Sens.xlsx: Created TIM DD worksheet with BE list and rx crit. Time

E NTGGGX083-RPT-001 Page 118 of 132 Appendix H - GGNS_R4B-Rel-Sens.rr Bayesian Data Data Sensitivity Study

ENTGGGX083-RPT-001 Page 119 of 132 TC Rate AOVCC 1.68E-03 AOVOC 3.68E-07 ASL DN 1.14E-03 ASP DN 4.08E-04 BAT LP 7.SOE-07 CBRCC 5.95E-03 CBRCO 1.04E-07 CBROO 3.79E-03 DGN Fl 3.42E-03 l)nit N

H N

N H

Description Dist Variance Prior Dist Air-Operated Valve@@@@

B 1.34E-06 B

Fails to Open Air-Operated Valve@@@@

G 3.67E-14 G

Transfers Closed Level Transmitter

@@@@ Fails on B

6.31E-07 B

Demand Pressure Transmitter B

1.59E-07 B

@@@@ Fails on Demand Battery @@@@

G 1.95E-13 G

Fails to Function Circuit Breaker

@@@@ Fails to B

1.19E-05 B

Open Circuit Breaker G

5.07E-15 G

Transfers Open Circuit Breaker

@@@@ Fails to B

7.28E-06 B

Close Diesel Generator

@@@@ Fails to G

1.87E G Run During the First Hour Data Sensitivity Study Prior Prior Prior Source FF Exposure Exp Mean Var.

Units NU REG/CR-9.SlE-04 8.llE-07 1

86 N

6928 v2010 N_UREG/CR-1.31E-07 2.SOE-14 3

4785372 H

6928 v2010 NU REG/CR-8.lSE-04 1.30E-05 2

1740 N

6928 v2010 1.17E-04 2.72E-07 NU REG/CR-.

1 2144 N

6928 v2010 5.86E-07 1.82E-13 NU REG/CR-

1 630864 H

6928 v2010 NU REG/CR-2.39E-03 5.93E-06 2

96 N

6928 v2010 NU REG/CR-2.llE-07 3.86E-14 1

15153679 H

6928 v2010 NU REG/CR-2.39E-03 5.93E-06 1

116 N

6928 v2010 3.78E-03 2.44E-07 NU REG/CR-4 2802 H

6928 v2010

ENTGGGX083-RPT-001 Page 120 of 132 TC Rate DGN FS 1.80E-03 EPVCC 4.21E-03 FNS FR 6.lSE-06 FNS FS 6.78E-04 MCS FS 3.31E-03 MDC FR l.18E-04 p

MDC FS P 5.33E-03 MDP FR 1.36E-06 Unit N

N H

N N

H N

H Description Dist Variance Prior Dist Diesel Generator

@@@@ Fails to B

3.21E-07 B

Start Explosive Valve

@@@@ Fails to B

7.04E-06 B

Open Fan {Standby)

@@@@ Fails to G

5.81E-12 G

Run After the First Hour Fan {Standby)

@@@@ Fails to B

1.29E-08 B

Start Motor-Driven Air Compressor (Standby)

B 6.87E-06 B

@@@@ Fails to Start Motor-Driven Air Compressor G

9.99E-10 G

@@@@ Fails to Run Motor-Driven Air Compressor B

l.09E-05 B

@@@@ Fails to Start Motor-Driven Pump@@@@

G 3.51E-13 G

Fails to Run Data Sensitivity Study Prior Prior Prior Source FF Exposure Exp Mean Var.

Units NU REG/CR-2.89E-03 1.03E-06 2

2802 N

6928 v2010 NUREG/CR-2.57E-03 4.38E-06 1

10 N

6928 v2010 4.54E-05 4.58E-10 NU REG/CR-2 958780 H

6928 v2010 NU REG/CR-8.42E-04 2.0SE-08 1

11371 N

6928 v2010 NU REG/CR-l.71E-02 4.76E-04 1

445 N

6928 v2010 8.SOE-05 3.61E-09 NU REG/CR-12 94821 H

6928 v2010 l.71E-02 4.76E-04 NU REG/CR-2 451 N

6928 v2010 NU REG/CR-3.53E-06 5.46E-12 3

3235768 H

6928 v2010

E NTGGGX083-RPT-001 Page 121 of 132 TC Rate

/

MDS FR 1.86E-05 MDS FS 1.06E-03 MOD CC 6.73E-04 MOVCC 5.SlE-04 MOVCO 1.89E-07 MOVOO 1.0SE-03 PTR LP 4.17E-07 TDP FR 7.lOE-06 Unit H

N N

N H

H Description Dist Variance Prior Dist Motor-Driven Pump (Standby)

@@@@ Fails to G

1.95E-10 G

Run After the First Hour Motor-Driven Pump (Standby)

B 2.83E-07 B

@@@@ Fails to Start Motor-Operated Damper@@@@

B 5.30E-08 B

Fails to Open Mot9r-Operated Valve@@@@

B 9.96E-08 B

Fails to Open Motor-Operated Valve@@@@

G 7.85E-15 G

Transfers Open Motor-Operated Valve@@@@

B 2.86E-07 B

Fails to Close Transformer

@@@@ Fails to G

8.88E-14 G

Function Main FW Turbine-Driven G

1.80E-11 G

Pump@@@@

Fails to Run Data Sensitivity Study Prior Prior Prior Source FF Exposure Exp Mean Var.

Units NU REG/CR-1.04E-05 1.39E-10 1

20668 H

6928 v2010 9.47E-04 4.61E-07 NU REG/CR-2 1677 N

6928 v2010 NU REG/CR-2.33E-04 3.SlE-08 6928 v2010 7

6064 N

NU REG/CR-9.63E-04 4.53E-07 6928 v2010 1

3404 N

NU REG/CR-3.39E-08 2.0lE-15 4

7266677 H

6928 v2010 NU REG/CR-9.63E-04 4.53E-07 2

1634 N

6928 v2010 NU REG/CR-9.44E-07 9.34E-13 1

3680044 H

6928 v2010 9.34E-06 4.86E-11 NU REG/CR-1 201600 H

6928 v2010

ENTGGGX083-RPT-001 Page 122 of 132 TC Rate TDS FS R 5.60E-03 TIM DD 2.SlE-06 Unit Description RCIC Turbine-Driven Pump N

(Standby)

@@@@ Fails to Start H

Timer@@@@

Fails to Operate Dist Variance Prior Dist B

l.OSE-05 B

G 2.53E-12 G

Data Sensitivity Study Prior Prior Prior Source FF Exposure Exp Mean Var.

Units NU REG/CR-6.49E-03 4.32E-05 2

381 N

6928 v2010 2.48E-05 l.23E-09 NU REG/CR-2 974798 H

6928 v2010

E NTGGGX083-RPT-001 Page 123 of 132 Data Sensitivity Study Appendix I - Data Source History and File Lists from Prior Models of Record

ENTGGGX083-RPT-001 Page 124 of 132 Item Rev3 GENERIC DATA: NUREG/CR-4550 (note 20); PlANT SPECIFIC DATA: Primary source for failures is Maintenance Rule, Estimated component exposures is Failure based on review of EPIX reports from 2001 -2006, PDS Data Used computer data, equipment rotation schedules, Shift Manager logs, system engineers, and PassPort tasks (note 21) Bayesian Updating performed when sufficient data exists Failure Data 1/1/2001 - 8/31/2006 period (note 20)

Covered Rev4 GENERIC DATA: NUREG/CR-6928, was the preferred source for the generic component failure data used in the GGNS PRA. This was supplemented with data from PRA-ES-01-001 and Resolution of MCR GG-4875 for generic failure rates not available in the NUREG. (Note 3) PLANT SPECIFIC DATA: Failure data was collected from September 1, 2006 through August 31, 2012 from the GGNS Maintenance Rule Database. The data was reviewed for functional failures and each failure was reviewed to determine if the failure met the definition of a failure as defined in the PRA. Demand data was obtained from the plant logs (Note 4) Generic data updated with Plant Specific Data when sufficient data available.

9/1/2006 - 8/31/2012 (note 1)

Data Sensitivity Study Rev4A Rev48 Current Sensitivity case GENERIC DATA: NUREG/CR-6928, was the preferred source for the generic

_component failure data used in the GGNS PRA. This was supplemented with data from PRA-ES-01-001 and Resolution of MCR GG-4875 for generic failure rates not available in the NUREG. (Note 5) PlANT GENERIC DATA: Same as SPECIFIC DATA: Failure data Rev. 48. PLANT SPECIFIC was collected from September DATA: Same as Rev. 48 l, 2006 through August 31, plus failure data collected 2012 from the GGNS Same as Rev.

from September 1, 2012 Maintenance Rule 4A through August 31, 2018 Database. The data was from the GGNS reviewed for functional Maintenance Rule failures and each failure was _

Database.

reviewed to determine if the failure met the definition of a failure as defined in the PRA.

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

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

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

ENTGGGX083-RPT-001 Page 125 of 132 Item Rev3 Rx-Cr it Hrs for 5.30 years Failure (note 22)

Data T&M Maintenance Rule database Unav Data (note 22) used 1/1/2001 - 8/31/2006 T&M (note 20)

Unav Data 1/1/2001 - 4/31/2005 period (note 22) - this is believed to Covered be in error based on App F calculations Rx-Cr it Hrs for 5.30 years T&M (note 23)

Unav Data Rev4 46,930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months (note 7)

Maintenance Rule Unavailability is used for systems tracked under the Maintenance Rule

/

program. For systems not tracked, a review of operational history (using CR database and operator logs) is used to determine 005 time (Note 11) 9/1/2006 - 8/31/2012 (note 1) 46,930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months (note 9)

Data Sensitivity Study Rev4A Rev48 Current Sensitivity case 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 (Note 8) 4A Maintenance Rule Maintenance Rule Unavailability is used for Unavailability is used for systems tracked under the systems tracked under the Maintenance Rule Maintenance Rule program. For systems not Same as Rev.

tracked, a review of 4A program. For systems not operational history (using CR tracked, it was assumed database and operator logs) is that the unavailability rate used to determine 005 time over time was the same as (Note 11) in Rev. 48 9/1/2006 - 8/31/2012 Same as Rev.

9/1/2006 - 8/31/2018 (note 2) 4A 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 (Note 10) 4A

ENTGGGX083-RPT-001 Page 126 of 132 Item Rev3 GENERIC: NUREG-6890/EPRI Reports (Loss of Offsite Power, Partial Loss of Offsite Power), NUREG/CR-5750

{LLO~A, Intermediate LOCA, SLOCA), WASH-1400 for Vessel Rupture, and PRA-ES-01-002 Rev 1 {Loss of AC Div 1/11, Loss of DC Div 1/11) (note

18) PLANT SPECIFIC: Plant specific data from last 5 years

{Transients with PCS available, Loss of Feedwater); Bayesian updated with Plant Specific Initiating data (Transients with Loss of Events PCS, Inadvertent Closure of Used MSIVs, Inadvertent Open SRV, Transients with Loss of Service Transformer); IEFTs (Loss of Plant Service Water, Loss of Component Cooling Water, Loss of Instrument Air, Loss of Service Transformer, Loss of Control Rod Drive, Loss of Turbine Building Cooling Water); Train level initiating for Loss of ac or de Div 1/11 buses are accounted for in the IEFTs and loss of FW, and loss of Service Transformer evaluations (note 18)

Rev4 GENERIC: NUREG/CR-6928 (Loss of Offsite Power,, Partial Loss of Offsite Power),

supplemented by NUREG/CR-5750 for those Initiating Events not in NUREG/CR-6928 (small-small LOCA, CRD Reference Leg Break) and NUREG-1829 for other LOCAs,

{Vessel Rupture, LLOCA, Intermediate LOCA, SLOCA)

(note 14) PLANT SPECIFIC:

Bayesian updated with Plant Specific data was used for Turbine/Reactor Trip, Loss of Condenser Vacuum, Loss of Feedwater, Inadvertent Closure of MSIVs, Inadvertent Open SRV, Loss of Division 1/11 vital ac buses, Loss of Division 1/11 vital de buses IEFTs were used for Loss of Plant Service Water, Loss of Component Cooling Water, Loss of Instrument Air, Loss of Service Transformer, Loss of Control

. Rod Drive, Loss of Turbine Building Cooling Water (note

14)

Data Sensitivity Study Rev4A Rev4B Current Sensitivity case GENERIC: NUREG/CR-6928 (Loss of Offsite Power, Partial Loss of Offsite Power),

supplemented by NUREG/CR-5750 for those Initiating Events not in NUREG/CR-6928 (small-small LOCA, CRD Reference Leg Break) and NUREG-1829 for other LOCAs (Vessel Rupture, LLOCA, Intermediate LOCA, SLOCA)

Initiating events summary

( note 15) PLANT SPECIFIC:

on the NRC website Bayesian updated with Plant (initiating-event-Specific data was used for Same as summary-2016.xlsx on Turbine/Reactor Trip, Loss of web page Condenser Vacuum, Loss of Rev. 4A htt~s:LLnrcoe.inl.govLresul Feedwater, Inadvertent tsdb/JnitEventL) and an Closure of MSIVs, lnadvert.ent LER search on the NRC Open SRV, Loss of Division 1/11 website (note 25) vital ac buses, Loss of Division--,

1/11 vital de buses IEFTs were used for Loss of Plant Service Water, Loss of Component Cooling Water, Loss of Instrument Air, Loss of Service Transformer, Loss of Control Rod Drive, Loss of Turbine Building Cooling Water (note

15)

ENTGGGX083-RPT-001 Page 127 of 132 Item Rev3 Initiating Events 7 /1/1986 - 8/30/2006.

Data (note 19) period Covered Rx-Cr it Hrs for 17.96 years Initiating (note 19)

Events Data Note 1 - From Section 2.0 of RSC 15-09 Rev 2 Rev4 5/22/2006 - 8/31/2012 (note

12) 49,188.06 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (Note 16)

c.

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

'Rev4A Rev4B 5/22/2006 - 8/31/2012 {note Same as Rev.

13) 4A 49,188.06 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Same as Rev.

(Note 17) 4A 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 Data Sensitivity Study Current Sensitivity case 5/22/2006 - 8/31/2018 (note 26) 10.37 reactor years

ENTGGGX083-RPT-001 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 Data Sensitivity Study 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 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 allrulet2c3.txt 11/14/2007 2:20:18 PM FGMASTGGR3.CAF 7/31/2007 11:21:20AM GGMutexcR3.txt 5/4/2007 2:47:47 PM GGNSR3 1E-12rec.qnt 12/17/2007 9:30:57 AM GGNSR3.RR 11/16/2007 12:58:33 PM GGR3 lE-12 baseline.cut 11/15/2007 7:47:16AM ggr3.caf 10/18/2007 10:08:03AM ggr3modules.cut 9/20/2007 6:05:39AM Data Sensitivity Study 61 Rev 3 recovery rules file.

61 Same as above.

7 Master flag file for Rev 3.

6 Mutually exclusive file for Rev 3.

45 Praquant control file for Rev 3.

2956 Rev 3 data base.

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.

271 Rev 3 fault tree.

224 Cutset file of Rev 3 modules.

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

Model Files:

Narne

~

GGNS_MOR_R4JF.rr

{a GGNS_MOR_R4_NoModJF.caf Flag File:

Name FLG_ GGNS_R4.txt Recovery Rule Files:

Narne GGNS FLOOD CUTSETS.txt GGNS INTERNAL EVENT CUTSETS.txt GGNS_MORJFCDF_R4f_ALL.txt GGNS_MOR_LERF _R4_HFE.txt GGNS_MOR_R4_LOSP.b.t Date m-odified Type 3/24/20113:54 PM CAFTA Database 3/22/2017 3:10 PM CAFT A Fault Tree

[}ate modified

Type 12/12/2016 8:43 AM Text Document Date modified Type 2/14/201711:21 AM Ted Document 2/14/201711:21 AM T e:1t Docurnent 3/23/2017 ;1.2:12 Pfv1 Ted Document 3/23/2017 2:47 Pfv1 Text: Docurnent 11/17/201611;;25..,

Text Document Size 75,020 KB 757 KB Size Size 1 KB 1 KB 2K8 122 KB 158 KB Data Sensitivity Study

E NTGGGX083-RPT-001 Page 131 of 132 Rev 4A MOR Files (PSA-GGNS-01-QU, Rev 2, Att A)

Model Files:

. FI..G_ GGNS_R4A-NOFlEX.txt GG[\\IS INTERNAL EVENT CUTSETS.txt GGNS Rev 4a CDF w LOOP..b.t

. GGNS Rev4a LERFw lOOP.trt ti) GGNS_R4A.rr I) GGNS_R4A_Seq-new IF.caf (I GGNS_R4A-new IF.caf 7/5/20l7 7:32 Afvt Ta1 Da.rnm1::nt:

7/25/2017 9:35 Af./t Text Document 1/19/2017 9:41 AIM T e..xt Document 7/20/2017 8:03 AJ,,,1 Text Docun1cnt 7/25/2{1171:18 P~./l CAFTA-Database 7/2.5./20l712:41 Pf\\,1 CAFTA Fault Tree 7/25/2:0l712:3H Pr>l1 CAFTA Fault tree 1 KB nrn KB KB 3,712 KB KB Data Sensitivity Study

E NTG GGX083-RPT-001

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

FLG~ GGNS_R4B-NOFLEX.txt GGNS Rev4B LERFw LOOP-IE Only.txt GGNS Rev 4B CDF w LOOP.trt GGNS Rev4B LERFw LOOP-IF Only.txt GGNS Rev48 LERFw LOOP.trt GGNS Rev 48 CDF w LOOP - IF only.. M FlG_GGNS_NOFLOOD.txt GGMS Rev4B CDF1,v LOOP-IE onl)'.txt

~

GGNS_R4B.rr

~ GGNS_R4B-new IF.ca.f IJ GGNS_R4B-new IF_Seq.caf 7/5/2:017 7:32 AM Text Document 1 '1/1/2018.2:4D PM T e.'<t Docurnent 11/1/2018 Text DooJment 11/1/20184:58 Pfv1 Text Dornrnent 11/1/2018 5:24 Pr*,,1 Text Docurnent 11/18/2.018 3:19 PJA CAFTA Database 11/18/2.018 3:17 Pfv1 C;AFTA Fault Tree

11/.18/20.18 3:*19 Pfvl CA.FTA Fault Tree 1 KB 191 KB 109 KB 1

KB 191 KB 2KB 1

7H4KB KB Data Sensitivity Study

v t e Letter Sequence Other
EPID:L-2018-LLA-0106, TSTF-425 (Approved, Closed)
Initiation Request, Request Acceptance, Acceptance Supplement Administration Questions 31 October 2018 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
MONTHYEAR2018-05-23 [Table View]

Person / Time
ML19066A088
Site:	Grand Gulf (NPF-029)
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

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

Text

Subject:

Enclosure:

References:

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