2CAN081007, Request for Additional Information Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716

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Request for Additional Information Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
ML102380446
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 08/24/2010
From: Giles M
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN081007, TAC ME3128, TAC ME3678
Download: ML102380446 (26)
v • d • e


Text

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4710 Mark A. Giles Manager, Licensing Arkansas Nuclear One 2CAN081007 August 24, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Request for Additional Information Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

REFERENCES:

1. Entergy letter to the NRC, dated January 20, 2010, Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 (2CAN011001) (TAC No. ME3128)
2. Entergy letter to the NRC, dated January 28, 2010, Supplement to Request for Alternative - Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 (2CAN011005)
3. Email from Kaly Kalyanam (NRC) to David B. Bice (Entergy), dated August 4, 2010, Request for Additional Information (TAC No. ME3678)

Dear Sir or Madam:

In letter dated January 20, 2010, Entergy Operations (Entergy) submitted a Request for Alternative to implement a risk-informed Inservice Inspection Program based on ASME Code Case N-716 (Reference 1). This letter was supplemented in its entirety due to an incorrect Inservice Inspection (ISI) sequence reference by letter dated January 28, 2010 (Reference 2).

During continued review of the request, the NRC determined that further information was required to complete the Staffs evaluation (Reference 3). Attachment 1 of this submittal contains the Reference 3 Request for Additional Information (RAI) along with Entergys response.

2CAN081007 Page 2 of 3 In addition to the technical questions issued in Reference 3, the NRC also requested updated commitment attachments to the Reference 1 and 2 letters above due to an inconsistency with the Arkansas Nuclear One (ANO) unit referenced in the attachments. Replacement pages for the Reference 1 and 2 letters are included in Attachments 2 and 3 of this letter. Please replace of the Reference 1 and 2 letters with the pages included in Attachments 2 and 3 of this submittal, respectively.

This letter contains no new commitments; however, the Reference 1 and 2 attachments containing the original commitments have been corrected to reference the correct ANO unit number.

If you have any questions or require additional information, please contact me.

Sincerely, Original signed by Mark A. Giles MAG/dbb Attachments:

1. Response to Request for Additional Information Related to Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
2. Replacement Page for Entergy Letter Dated January 20, 2010, Attachment 2 (2CAN011001)
3. Replacement Page for Entergy Letter Dated January 28, 2010, Attachment 2 (2CAN011005)

2CAN081007 Page 3 of 3 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205

Attachment 1 to 2CAN081007 Response to Request for Additional Information Related to Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 to 2CAN081007 Page 1 of 17 Response to Request for Additional Information Related to Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716

1. In Appendix 1 of the submittal, the disposition to IF-A1-01 states that the ANO-2 internal flooding analysis has been completed and has been performed in accordance with the accepted methodology used at Waterford-3 and therefore the issue is considered to be resolved. Based on the information provided in the submittal, the staff does not have sufficient information to characterize the quality of the internal flooding PRA for ANO-2. Since this application is dependent on the flooding portion of the PRA, the staff requests that, based on RG 1.200 guidelines, the licensee perform a focus-scope gap assessment on the internal flooding portion of the updated PRA model. The gap assessment should assess the capability category for each supporting requirement for the updated internal flooding PRA based on the ASME standard. In addition, provide a disposition related to this application for any supporting requirements that are not met.

The methodology adopted in this internal flooding analysis is in broad accord with the requirements of the ASME PRA Standard and the EPRI Guidelines. In general, Capability Category II requirements have been met although Capability Category III supporting requirements are met in some instances. Some instances are more conservative than the guidelines suggest (e.g., consideration of the effect of spray over and above flooding, and allowance for spray to reach equipment at a 30 distant from the point of rupture rather than the 10 or 20 suggested by the EPRI Guidelines. The basis for the information presented below was obtained from the ANO-2 Internal Flooding Analysis.

Since the ANO-1 and ANO-2 flooding analyses were performed sequentially using the same basic approach, the Capability Category provided in the table below is based upon:

1) the peer review findings from the ANO-1 Internal Flooding Analysis, and 2) Entergys review of each of the supporting requirements (SRs) in relation to the ASME/ANS standard. In some cases, the Capability Category presented below for ANO-2 differed from that of ANO-1 peer review findings. This difference is due to lessons learned that were implemented during the ANO-2 analysis. Those differences are identified and discussed in the table below.

All High Level Requirements (HLR) for the Internal Flood Analysis have been met for ANO-2. The SRs discussed in the table below provide validation that these HLRs are met. Entergy has identified a reasonable set of plant flood areas, identified and characterized flood sources, developed flood scenarios and propagation paths, identified applicable SSCs with their appropriate flood induced failure modes, calculated the frequencies of flood events, and quantified the scenarios per the ASME/ANS standard.

While enhancements are required relating to documentation of uncertainties, the results of our analysis remain valid and do not impact the request for approval of the fourth ten-year interval Inservice Inspection (ISI) Program.

to 2CAN081007 Page 1 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFPP-A1: define flood areas Potential flood zones were identified by dividing the major buildings and All areas into room areas according to their elevations and whether they are enclosed. Structural considerations, such as walls and doors were used to identify the boundaries. While flood zones have some degree of independence, particularly with regard to spraying and environmental effects, they may also have interconnections (doors, drains, etc.) that lead to flood propagation. In the analysis, individual rooms were not necessarily considered to be individual flood zones, if there is no impediment to the propagation of floodwater into adjoining areas. The flood areas are identified by building (auxiliary, turbine, intake), elevation, then a unique number.

IFPP-A2: define flood areas at the level Flood areas defined at the level of individual rooms or combined rooms for II/III of individual rooms or combined rooms which plant design features exist to restrict flooding.

IFPP-A3: for multi-unit sites with shared Fire water pumps are shared between both units; Units 1 and 2 are All systems or structures, include multi-unit physically connected on multiple elevations. The spent fuel area for Units 1 areas (flood zone AB404-159) and 2 (flood zone AB404-2151) are continuous.

Floodwater released into either spent fuel pool area will flow preferentially into the Unit 1 spent fuel pool. Although a 4 curb surrounds the pool, this curb has numerous gaps and would not prevent even small releases from entering the fuel pool. Also, service water return piping for Unit 2 traverses the 335 elevation of Unit 1.

IFPP-A4: use plant information sources Plant architectural, construction and drain drawings were used in All used to reflect the as-built as-operated conjunction with a plant walkdown to identify flood areas. Plant drawings plant to support development of flood are included in the internal flood documentation.

areas to 2CAN081007 Page 2 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFPP-A5: conduct a plant walkdown A plant walkdown was conducted. Notes were developed from the All walkdown, a review of plant drawings, and a review of other documents. It should be noted that for operational and health reasons, not all rooms were entered. For those rooms not entered, architectural drawings were utilized.

IFPP-B1: document plant partitioning Flood zones resulting from plant partitioning are documented by list and All visually on plant drawings contained in the internal flood analysis.

IFPP-B2: document process to identify The process to define flood zones is documented in the internal flood All flood areas analysis. The process started with rooms and then combined rooms, if the rooms are interconnected through drains or other means.

IFPP-B3: document sources of The plant walkdowns provide confirmation of the plant partitioning and the Not Met uncertainty and assumptions interconnections of the various rooms in the plant. The assumptions on flood barriers are clearly documented in the internal flood analysis as well as the flood propagation pathways.

However, sources of model uncertainty and related assumptions were not documented for the internal flood analysis.

While documenting and understanding sources of model uncertainty is critical in ultimately ensuring that application results are understood and utilized in a manner that is defensible in relation to the application.

This SR, although important for developing a thorough understanding of the results, does not affect the ANO-2 results for the following reasons and will be included in future revisions to the Internal Flood Analysis:

(continued) to 2CAN081007 Page 3 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFPP-B3: document sources of 1) The sizes of flood sources were first determined assuming guillotine uncertainty and assumptions breaks of lines or the catastrophic rupture of valves, tanks, gaskets, (continued) fittings and heat exchangers. This approach is consistent with the NRC Standard Review Plan, Sections 3.6.1 and 3.6.2, for high-energy lines and components, but is more conservative than the NRC Standard Review Plan for the medium energy lines that are of principal concern in this analysis.

2) No flood area was screened out based upon the basis of operator action.
3) Flow rates were taken as a maximum flow capacity for the propagation path.
4) A plant scram was assumed for each flood scenario.
5) In general floods were allowed to persist for long periods of time

(~ 12 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) unless the flood source is finite.

6) Uncertainty analysis does not affect the results.

IFSO-A1: identify the potential sources The potential sources of flooding were identified from drawings, walkdowns, All of flooding and lists of systems and equipment in each flood zone. Propagation from adjacent rooms is included. The Dardanelle Reservoir was considered as an external flood source.

IFSO-A2: for multi-unit sites with shared Rupture scenario involving Unit 2 service water return as it traverses the All systems or structures, include potential 335 elevation of Unit 1 is addressed in the internal flood analysis. See also sources with multi- or cross-unit impact IFPP-A3.

to 2CAN081007 Page 4 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFSO-A3: screen out areas with no Areas with no flood source have been screened out (except as a potential All potential source of flooding flood propagation path).

IFSO-A4: for each potential source of Flooding mechanisms were not identified in the internal flood analysis. A N/A flooding identify the flooding conservative approach was taken to assume a flood is always possible; the mechanisms flood rupture frequencies assumed incorporate all sources of flooding.

IFSO-A5: for each source and its failure The sizes of flood sources were first determined assuming guillotine breaks All mechanism identify the characteristic of of lines or the catastrophic rupture of valves, tanks, gaskets, fittings and the release and capacity of the source heat exchangers; where the volume of floodwater that might be released is finite, this fact was noted in the analysis. A flood source flows at full flow until it is isolated or its water supply is limited or exhausted.

IFSO-A6: conduct a plant walkdown A plant walkdown was conducted. The internal flood analysis contains the All notes developed from this and the review of plant drawings and other documents. It should be stressed that for operational and health reasons, not all rooms were entered. For those rooms not entered architectural drawings were utilized.

IFSO-B1: document the internal flood The source of each flood scenario including the pipe segment or equipment, All sources system, rupture type and capacity is described in the description of each scenario in the analysis.

IFSO-B2: document process to identify The potential flood sources were identified and documented in relation to the All flood sources flood areas where the source is located.

IFSO-B3: document uncertainty and The analysis assumes that all flooding sources are included in the Not Met assumptions calculation of the flood frequency. By considering the guillotine rupture of lines, it is ensured to address the fact that catastrophic failures capture the failures associated with operator error or design and construction errors, corrosion, erosion, impact and hanger failure, and other noted causes of line rupture, and the possibility of lesser cracks growing to guillotine ruptures. if subjected to dynamic loads. Also see response to IFPP-B3.

to 2CAN081007 Page 5 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFSN-A1: for each defined flood area The propagation path(s) from each flood source area to its area of All and flood source, identify the accumulation are identified and presented in schematics within the internal propagation path from the flood source flood analysis.

area and its area of accumulation IFSN-A2: for each flood area and each Plant design features able to terminate or contain the flood propagation All source, identify plant design features have been identified and discussed in relation to the flood area or flood able to terminate or contain the flood scenario where they affect the movement of floodwater.

propagation IFSN-A3: for each flood area and each Automatic or operator responses able to terminate or contain the flood All source, identify automatic or operator propagation were identified in conjunction with the flood scenario that responses able to terminate or contain necessitates the automatic or human response. However, only four specific the flood propagation cases were evaluated to take credit for an operator action to stop the flooding. In these specific cases, criteria were established for utilizing an operator action for mitigating the flood. Those criteria are 1) Operations must have obvious indication in the control room that a problem exists,

2) the flood condition is easily identified, 3) procedures exist for mitigating the flood scenario, and 4) the actions taken by the operators are not significantly affected by the flood condition. All other scenarios took no credit for terminating the flood. The flooding was assumed to continue for 12-24 hours or until the volume of the source had been depleted.

IFSN-A4: estimate the capacity of The amount of water retained by sumps etc. were accounted for in All drains and the amount of water retained determining the consequences of internal flooding. In general, drains were by sumps, etc. assumed to not function unless their functioning exacerbates the situation.

IFSN-A5: identify the SSCs addressed The structures, systems, and components (SSCs) addressed in the PRA in All in the PRA in each flood area each flood area and their susceptibility to flooding and spray damage were identified in the flooding analysis.

to 2CAN081007 Page 6 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFSN-A6: determine for the SSCs The susceptibility to flood and spray damage was considered; with jet III addressed in the PRA their impingement, pipe whip, temperature, and humidity considered in High susceptibility to flooding and spray Energy Line Breaks. Specifically, jet impingement is considered as a result This SR was damage of main feedwater line breaks in the steam pipe and water heater area; pipe identified as whip is considered as a result of main steam system ruptures in the steam not met in the pipe area; temperature and humidity are considered as a result of main ANO-1 Peer steam system ruptures in the steam piping area, upper north piping Review.

penetration area, electrical equipment room, chiller room, heat exchanger However, the area, Emergency Feedwater (EFW) B pump room, electrical switchgear ANO-2 area, water heater and compressor areas, main feedwater line ruptures in analysis the chiller equipment room, pipeway, water heater area, upper north piping addressed penetration area and hallways, and ruptures of the chemical and volume the identified control system in the piping penetration area and heat exchanger rooms. weakness in development of the analysis.

IFSN-A7: take credit only as appropriate Credit taken as appropriate. Each class of component (motor-operated All for the availability of SSCs valves (MOV), air-operated valves (AOV), hydraulic valves, manual and check valves, motor and turbine pumps, compressors, fans diesel engines, instrumentation, electrical equipment, cables, junction boxes, heat exchangers, tanks, piping, ductwork, room air coolers, heaters, air ejectors, oil separators, etc) is assessed under submergence, spray and steam failure mechanisms. In addressing the rupture of high energy lines we have relied extensively on the analysis of pipe whip, jet impingement and other HELB issues in the Safety Analysis Report (SAR).

IFSN-A8: identify inter-area propagation Inter-area propagation identified including doors, hatches, drains, and other II penetrations. It was assumed that at low water depths, flow into a drain resembles flow over a broad-crested weir. Flow through constriction across the floor in a given zone was modeled as flow through an open channel.

to 2CAN081007 Page 7 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFSN-A9: perform any necessary Engineering calculations were performed as necessary to assess capability All engineering calculations for flood rate, of SSCs. The analysis relies on some outside calculations (i.e. when a door etc will fail due to differential water height and flow through drains and across flood areas)

IFSN-A10: develop flood scenarios Flood scenarios were developed including flood area, source, flood rate, All operator actions, and SSC damage (due to flood and independent causes).

Propagation paths were included in the development as well as the SSCs in the propagation path susceptible to the flood progression.

IFSN-A11: for multi-unit sites with Fire water pumps in Unit 1 intake structure serve both units. Ruptures All shared systems or structures, include involving these pumps, a rupture scenario involving Unit 2 service water multi-unit scenarios return as it traverses the 335 elevation of Unit 1, and the propagation of floodwater across 404 elevation are addressed in the ANO-1 internal flooding analysis. See also IFPP-A3 IFSN-A12/IFSN-A13: Screen out flood No flood areas were screened out All areas IFSN-A14: do not screen out flood No flood areas were screened out III areas based on a reliance on operator actions IFSN-A15: screen out flood sources No flood sources were screened out All based on specific conditions IFSN-A16: do not screen out flood No flood sources screened out in this instance because the mitigating III sources based on a reliance on effects of the inspection and replacement programs were not addressed (i.e.

operator actions there is no data to quantify these effects).

IFSN-A17: conduct a plant walkdown A plant walkdown was conducted. The internal flood analysis contains the All notes developed from the waldown and the review of plant drawings and other documents.

to 2CAN081007 Page 8 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFSN-B1: document flood scenarios Flood scenarios are documented individually including the source, SSCs All affected, and operator actions.

This SR was identified as not met in the ANO-1 Peer Review.

However, the ANO-2 analysis addressed the identified weakness in development of the analysis.

IFSN-B2: document process to identify The process to identify flood scenarios is explained in the internal flood All applicable flood scenarios analysis before any of the scenarios are described. The process includes identification of flood area, flood source, propagation path, SSCs in that path, and human actions that can be credited.

IFSN-B3: document uncertainty and Assumptions made in the process to identify flood scenarios are listed after Not Met assumptions the description of the identification process. The list includes assumptions on flood flow rates, the radius of damage for spray scenarios, treatment of drains, etc. Also, in general, no credit was taken for drains as a way in which floods might be mitigated. Their blockage so as to allow water to flow between flood zones on a given elevation was considered. Also see response to IFPP-B3.

to 2CAN081007 Page 9 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFEV-A1: for each flood scenario The corresponding plant initiating event group is listed in each scenario All identify the corresponding plant initiating description in the internal flooding analysis.

event group IFEV-A2: group flooding scenarios Flooding scenarios were not grouped in the internal flooding analysis. III IFEV-A3: group or subsume flood Grouped flood scenarios with an existing plant initiating event group when I/II scenarios with an existing plant initiating applicable (e.g. %T19 Loss of Component Cooling Water Loop II, %T5-A, event group. B and C, Feedwater line break initiators, %RCP Reactor coolant pump seal This SR was LOCA); however, no scenarios were subsumed. identified as not met in the ANO-1 Peer Review.

However, the ANO-2 analysis addressed the identified weakness in development of the analysis.

IFEV-A4: for multi-unit sites with shared Rupture scenario involving Unit 2 service water return as it traverses the All systems or structures include multi-unit 335 elevation of Unit 1 is addressed in the internal flooding analysis. See impacts also IFPP-A3 IFEV-A5: determine the flood initiating Rupture frequencies were calculated for each line or piece of equipment that All event frequencies might rupture, using EPRIs Pipe Rupture Frequency for Internal Flooding PRAs in which a number of flood flow rates and matching rupture frequencies are presented for lines of different size and in different service and for other equipment.

to 2CAN081007 Page 10 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFEV-A6: gather and use plant-specific Plant-specific information was used in determining flood initiating event II/III information in determining flood frequencies. The specific line size and length was used with the EPRI initiating event frequencies method to determine flood initiating event frequency. This SR was identified as not met in the ANO-1 Peer Review.

However, the ANO-2 analysis addressed the identified weakness in development of the analysis.

IFEV-A7: include a consideration of By considering the guillotine rupture of lines, we ensure that we Not Met human induced floods during address the fact that catastrophic failures capture the failures maintenance through the application of associated with operator error (e.g., maintenance-induced floods) or generic data design and construction errors (such as water hammer, the improper handling of dynamic loads, or undetected fabrication errors), corrosion, erosion, impact and hanger failure and other noted causes of line rupture and the possibility of lesser cracks growing to guillotine ruptures if subjected to dynamic loads. While maintenance-induced floods and water hammer-induced valve or pipe rupture resulting from the creation of voids in containment spray and low pressure safety injection systems are of particular concern and while the need to assess human induced floods in relation to the application of the generic data is important for ensuring that the flood frequency is inclusive, the inclusion of these human induced floods has no bearing on the susceptible damage mechanisms associated with ISI examinations.

(continued) to 2CAN081007 Page 11 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFEV-A7: include a consideration of EPRI TR-1013141 Pipe Rupture Frequencies for Internal Flooding PRAs human induced floods during was used to develop the rupture frequency for piping. This document, maintenance through the application of states, All piping system pressure boundary failures have been included generic data (continued) including failures in pipe base metal, welds, and other metallic pressure boundary components such as valve bodies, heat exchangers, and fittings.

Human induced causes of flooding that do not involve piping system pressure boundary failure such as overfilling tanks and inappropriate valve operations that release fluid from the system are not included. Such events are expected to be included in the human reliability analysis for the internal flood PRA as they are design and procedure specific, and should not be buried in the component failure data.

This SR will be addressed in a future update to the Internal Flood Analysis.

This SR has no affect on the RI-ISI submittal for ANO-2 since the generic data includes all piping system pressure boundary failures including those that are human induced. Also, IFEV-A7 is not considered required per EPRI 1018427, Table 2-2, for technical adequacy of PRAs used to develop RI-ISI programs.

to 2CAN081007 Page 12 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFEV-A8: screen out flood scenarios Conservative screening rules were used to eliminate internal flooding events All based on quantitative and other criteria with a limited potential for core damage. Releases from normally isolated lines were not developed, if they would not precipitate a plant shutdown. This SR was Flooding scenarios were not eliminated, however, because of their low identified as probability of occurrence or because they could be subsumed into other not met in the initiating events. The predicted frequency of a rupture was not used to ANO-1 Peer screen out any accident scenario. Review.

However, the ANO-2 analysis addressed the identified weakness in development of the analysis.

IFEV-B1: document flood induced Every flood scenario is either assumed to cause a plant trip or is grouped All initiating events with an initiator that has identical consequences to plant systems.

IFEV-B2 document process to identify The supporting documents for the internal flood analysis contain the flood All flood induced initiating events frequencies and the flood unique data.

IFEV-B3: document uncertainty and See response to IFPP-B3 Not Met assumptions to 2CAN081007 Page 13 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFQU-A1: review accident sequences to The quantification of the internal flood model is performed by application of All confirm applicability specific flag files in the base internal events model. This is documented in the internal flooding analysis. The accident sequences for the flood events are similar to those sequences used in the base internal events model and were confirmed to align with the initiating events used in each flooding scenario. Resultant cutsets were used to verify the expected accident progressions.

IFQU-A2: Modify systems analysis to System failures are set using flags in the Internal Flooding Analysis. Use of All include flood induced failures flags in the base PRA model ensures that the same level of detail is provided from the systems analysis as is used in quantification of the baseline PRA.

IFQU-A3: Limit the use of quantitative No quantitative screening of scenarios was performed in the internal flood N/A screening of flood areas analysis. A 10-12/ry truncation limit was applied in quantification. Once quantified, the results of the individual scenarios were incorporated into the No overall results. quantitative screening was performed IFQU-A4: perform additional analysis of Additional analysis of door failure was used from ANSI/BHMA calculations All SSC data if necessary that prove to be the industry standard.

to 2CAN081007 Page 14 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFQU-A5: add human reliability analysis It is generally assumed that if operators have indication of a flooding event, All if necessary that in may cases they would be capable of isolating the flow within 15 minutes. However, the internal flood analysis conservatively assumes This SR was that the flooding will proceed for 12 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or to the capacity of the identified as flood source in all but four cases. For those four cases, criteria were not met in the established for utilizing an operator action for mitigating the flood. Those ANO-1 Peer criteria are 1) Operations must have obvious indication in the control room Review.

that a problem exists, 2) the flood condition is easily identified, However, the

3) procedures exist for mitigating the flood scenario, and 4) the actions ANO-2 taken by the operators are not significantly affected by the flood condition. analysis addressed the identified weakness in development of the analysis.

IFQU-A6: include scenario specific This SR is interpreted to imply that any mention of the use of operator All PSFs on human reliability analysis actions to isolate flooding sources in a given amount of time should undergo some type of human reliability analysis. Only two new Human Reliability Analyses (HRAs) were added to the model to credit isolation of the flooding source. Operator interviews were conducted, the HRA toolbox was used, and the criteria discussed in IFQU-A5 were used to ensure that a reasonable probability of failure was calculated for these two events.

IFQU-A7: perform sequence Flood scenario quantification was performed with CAFTA and PRAQuant. All quantification The results are reported extensively in the internal flood analysis documentation.

to 2CAN081007 Page 15 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFQU-A8: include flooding failures with The effect of each flooding scenario is dependent on the flood induced All independent causes failures specific to the scenario and on the independent failures of components necessary for the mitigation of the flood scenario. The independent failures can be due to maintenance unavailability or common cause or other source.

IFQU-A9: include effects of flooding Direct and indirect effects are considered. The effects of spraying and All splashing from a flood were assumed to be restricted to within 30of the source. Pipe whip is considered for failures (ex. letdown lines). It is noted that the SAR is relied upon for indirect effects from high energy lines.

IFQU-A10: review LERF analysis to The ANO-2 PRA model links the Level 1 and Level 2 results into a single All confirm applicability fault tree file. The top gates for Level 1 is CORE DAMAGE and the top gate for Level 2 is Large Early Release Frequency (LERF). The flag files are set This SR was during the quantification for Level 1 and Level 2 results. Since the LERF identified as portion of the tree is quantified in a similar manner to that for Level 1, the not met in the flag files used in the quantification are the same, and the LERF sequences ANO-1 Peer are not altered by the flood analysis (only the flood failures affecting the Review.

probability of a Level 1 endstate and the flood failures affecting the LERF However, the mitigation components are affected in the flood analysis), the quantification ANO-2 of the Level 2 results are valid. The results of the LERF analysis when analysis related to the corresponding Core Damage Frequency (CDF) provide addressed additional validation of the relative nature of the results. the identified weakness in development of the analysis.

IFQU-A11: conduct walkdowns A plant walkdown was conducted. The internal flood analysis contains the All notes developed from this and the review of plant drawings and other documents.

to 2CAN081007 Page 16 of 17 Matching of Supporting Requirements in the ASME PRA Standard Capability Supporting Requirement Index No. How Addressed Category IFQU-B1: document accident The flooding scenarios are documented including the flood source, type of All sequences and quantification source, mitigation efforts (automatic and human), affected SSCs and affect on the plant of the system made unavailable by the flood event.

IFQU-B2: document process to define The quantification process including how the flag files are used, how the top All accident sequences and quantification logic is modified and how each scenario is quantified is described in detail in the methodology section of the Quantification appendix of the internal flood analysis.

IFQU-B3: document uncertainty and See response to IFPP-B3. Not Met assumptions to 2CAN081007 Page 17 of 17

2. Were new examination locations identified, if so, were the new examination locations included in the change in risk estimate? Using an upper-bound estimate for new locations would be non-conservative. Please demonstrate that this non-conservative approach, if corrected, would not exceed the delta risk guidelines New locations were added. The following is stated on Page 16 of 25 in Attachment 1 of the request:

Also, for cases where the RIS_B selections exceeded SXI selections in Table 3.4-1, they were set equal to SXI to confirm that the use of conservative CCDP and CLERP are not non-conservative relative to meeting the acceptance criteria.

To expound, certain Chemical and Volume Control (CH), Main Feedwater (MFW),

Reactor Coolant (RCS), and Safety Injection (SI) entries in Table 3.4-1 indicate the risk-informed / safety-based ISI (RIS_B) selections to be greater than those of ASME Code Section XI (SXI) (i.e., the Delta column has a positive number). These entries were revised by setting the positive Delta values to zero. This conservative change in risk sensitivity calculation was performed in lieu of a lower bound calculation to show that the acceptance criteria is met with the use of conservative Conditional Core Damage Probability (CCDP) and Conditional Large Early Release Probability (CLERP) and that the number of RIS_B selections not allowed to exceed SXI.

Attachment 2 to 2CAN081007 Replacement Page for Entergy Letter Dated January 20, 2010, Attachment 2 (2CAN011001) to 2CAN011001 Page 1 of 1 LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Entergy in this document.

Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.

SCHEDULED COMMITMENT TYPE COMPLETION (Check one) DATE ONE-TIME CONTINUING ACTION COMPLIANCE ANO-2 is in the process of evaluating 9 June 30, 2011 MRP-146, Materials Reliability Program:

Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines, and these results will be incorporated into the RIS_B Program, as warranted.

The request for alternative pertaining to 9 Upon NRC the use of Code Case N-578 will be approval of this withdrawn for use at ANO-2 upon NRC request for approval of the RIS_B Program submittal. alternative Upon approval of the RIS_B Program, 9 Upon NRC procedures that comply with the guidelines approval of this described in EPRI TR-112657 will be request for prepared to implement and monitor the alternative program.

Attachment 3 to 2CAN081007 Replacement Page for Entergy Letter Dated January 28, 2010, Attachment 2 (2CAN011005) to 2CAN011005 Page 1 of 1 LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Entergy in this document.

Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.

SCHEDULED TYPE COMMITMENT COMPLETION (Check one)

DATE ONE-TIME CONTINUING ACTION COMPLIANCE ANO-2 is in the process of evaluating 9 June 30, 2011 MRP-146, Materials Reliability Program:

Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines, and these results will be incorporated into the RIS_B Program, as warranted.

The request for alternative pertaining to 9 Upon NRC the use of Code Case N-578 will be approval of this withdrawn for use at ANO-2 upon NRC request for approval of the RIS_B Program submittal. alternative Upon approval of the RIS_B Program, 9 Upon NRC procedures that comply with the guidelines approval of this described in EPRI TR-112657 will be request for prepared to implement and monitor the alternative program.

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