ML081350177

Response to Request for Supplemental Information Associated with Relief Request 14R-44

ML081350177
Person / Time
Site:	Peach Bottom
Issue date:	05/13/2008
From:	Cowan P Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML081350177 (19)

Text

Exelon Nuclear wwwexeloncorp.com 200 Exelon Way Kennett Square, PA 19348 10 CFR 50.55a May 13, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278

Subject:

Response to Request for Supplemental Information Associated with Relief Request 14R-44

Reference:

1) Letter from P. B. Cowan (Exelon Generation Company, LLC) to U. S.

Nuclear Regulatory Commission, "Submittal of Relief Requests Associated with the Third and Fourth Inservice Inspection (lSI) Intervals and the First and Second Containment Inservice Inspection (CISI) Intervals," dated February 29,2008

2) Letter from J. D. Hughey (U. S. Nuclear Regulatory Commission) to C. G.

Pardee (Exelon Generation Company, LLC), "Peach Bottom Atomic Power Station, Units 2 and 3 - Request for Supplemental Information Regarding Relief Request 14R-44 (TAC NOS. MD8296 and MD8297)," dated May 7, 2008 In the Reference 1 letter, Exelon Generation Company, LLC (EGC) submitted for your review and approval relief requests associated with the third and fourth Inservice Inspection (lSI) intervals for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. Also included for your review and approval were relief requests associated with the first and second Containment Inservice Inspection (CISI) intervals for PBAPS, Units 2 and 3.

In a conversation with the U.S. Nuclear Regulatory Commission staff on April 29, 2008, supplemental information was requested as part of the acceptance review of Relief Request

Relief Requests Associated with Third and Fourth lSI Intervals and First and Second CISllntervals May 13, 2008 Page 2 14R-44 concerning the risk-informed inservice inspection program at PBAPS, Units 2 and 3. A summary of this request is contained in the Reference 2 letter. Attached is our response to this request. There are no regulatory commitments contained in this letter.

Should you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.

Respectfully, Pamela B. Cowan Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1) U. S. NRC Request for Supplemental Information Concerning Relief Request 14R-44

2) Response to Request for Supplemental Information Concerning Relief Request 14R-44 cc: S. J. Collins, Regional Administrator, Region I, USNRC F. Bower, USNRC Senior Resident Inspector, PBAPS J. Hughey, Project Manager, USNRC S. T. Gray, State of Maryland R. R. Janati, Commonwealth of Pennsylvania

ATTACHMENT 1 U. S. NRC Request for Supplemental Information Concerning Relief Request 14R-44

U. S. NRC Request for Supplemental Information Regarding Relief Request 14R-44 Page 1 of 1 REQUEST FOR SUPPLEMENTAL INFORMATION REGARDING RELIEF REQUEST 14R-44 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 Question:

By letter to the Nuclear Regulatory Commission (NRC) dated February 29, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML08064058), Exelon Generation Company, LLC (the licensee), submitted a Request for Alternative 14R-44. The Request for Alternative 14R-44 proposes a risk-informed (RI) selection and examination program as an alternative to a portion of its current inservice inspection (lSI) program for Peach Bottom Atomic Power Station, Units 2 and 3, on the basis that the alternative provides an acceptable level of quality and safety. Exelon requests to implement an RI-ISI program based on the Revised Risk-Informed Inservice Inspection Evaluation Procedure (EPRI TR-112657, Revision B-A, December 1999).

NRC staff review of proposed RI-ISI programs is performed in accordance with Regulatory Guide (RG) 1.178, "An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping," Revision 1, September 2003 (ADAMS Accession No. ML032510128). RG 1.178 states that, when completed, Draft Guide DG-1122, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities," will provide guidance on determining the quality of the probabilistic risk assessment (PRA) that is sufficient to provide confidence in the results such that they can be used in regulatory decision-making for light-water reactors. DG-1122 was issued as RG 1.200, Revision 1, in January 2005 (ADAMS Accession Nos. ML070240001 and ML071940235). As clarified in Regulatory Issue Summary 2007-06, "Regulatory Guide 1.200 Implementation,"

issued March 22, 2007 (ADAMS Accession No. ML070650428), the NRC staff will use Revision 1 of RG 1.200 to assess technical adequacy for all RI applications received after December 2007.

In order to make the application complete, the NRC requests that the licensee supplement the application to address the quality of the PRA utilized for Alternative Request 14R-44.

Response

Supplemental information to address the quality of the PRA utilized for Relief Request 14R-44 is contained in Attachment 2.

ATTACHMENT 2 Response to Request for Supplemental Information Concerninq Relief Request 14R-44

Attachment 2 Response to Request for Supp/ementa//nformation Concerning Relief Request /4R-44 Summary Statement of Peach Bottom Atomic Power Station, Units 2 and 3 PRA Model Capability for Use in Risk-Informed Licensing Actions Introduction Exelon Generation Company (EGC) employs a multi-faceted approach to establishing and maintaining the technical adequacy and plant fidelity of the PRA models for all operating EGC nuclear generation sites. This approach includes both a proceduralized PRA maintenance and update process, and the use of self-assessments and independent peer reviews. The following information describes this approach as it applies to the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 PRA.

PRA Maintenance and Update The EGC risk management process ensures that the applicable PRA model remains an accurate reflection of the as-built and as-operated plants. This process is defined in the EGC Risk Management program, which consists of a governing procedure (ER-AA-600, ll IIRisk Management and subordinate implementation procedures. EGC procedure ER-

)

ll AA-600-1015, IIFPIE PRA Model Update delineates the responsibilities and guidelines for updating the full power internal events PRA models at all operating EGC nuclear generation sites. The overall EGC Risk Management program, including ER-AA-600-1015, defines the process for implementing regularly scheduled and interim PRA model updates, for tracking issues identified as potentially affecting the PRA models (e.g., due to changes in the plant, errors or limitations identified in the model, industry operating experience), and for controlling the model and associated computer files. To ensure that the current PRA model remains an accurate reflection of the as-built, as-operated plants, the following activities are routinely performed:

• Design changes and procedure changes are reviewed for their impact on the PRA model.

• New engineering calculations and revisions to existing calculations are reviewed for their impact on the PRA model.

• Maintenance unavailabilities are captured, and their impact on CDF is trended.

• Plant specific initiating event frequencies, failure rates, and maintenance unavailabilities are updated approximately every four years.

In addition to these activities, EGC risk management procedures provide the guidance for particular risk management and PRA quality and maintenance activities. This guidance includes:

• Documentation of the PRA model, PRA products, and bases documents.

• The approach for controlling electronic storage of Risk Management (RM) products including PRA update information, PRA models, and PRA applications.

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Attachment 2 Response to Request for Supp/ementa//nformation Concerning Relief Request /4R-44

• Guidelines for updating the full power, internal events PRA models for EGC nuclear generation sites.

• Guidance for use of quantitative and qualitative risk models in support of the On-Line Work Control Process Program for risk evaluations for maintenance tasks (corrective maintenance, preventive maintenance, minor maintenance, surveillance tests and modifications) on systems, structures, and components (SSCs) within the scope of the Maintenance Rule (1 OCFR50.65 (a)(4)).

In accordance with this guidance, regularly scheduled PRA model updates nominally occur on an approximately 4-year cycle; longer intervals may be justified if it can be shown that the PRA continues to adequately represent the as-built, as-operated plant.

EGC will be performing a regularly scheduled update to the PBAPS PRA model in 2009, which is expected to be approved by early 2010.

PRA Self Assessment and Peer Review Several assessments of technical capability have been made, and continue to be planned, for the PBAPS, Units 2 and 3 PRA models. These assessments are as follows and further discussed in the paragraphs below.

• An independent PRA peer review was conducted under the auspices of the BWR Owners Group in 1998, following the Industry PRA Peer Review process [1]. This peer review included an assessment of the PRA model maintenance and update process.

• In 2004, a gap analysis was performed against the available version of the ASME PRA Standard [2] and the draft version of Regulatory Guide 1.200, DG-1122 [3]. In 2006, an assessment of the extent to which the previously defined gaps had been addressed was performed in conjunction with a PRA model update.

• During 2005 and 2006 the PBAPS, Units 2 and 3 PRA model results were evaluated in the BWR Owners Group PRA cross-comparisons study performed in support of implementation of the mitigating systems performance indicator (MSPI) process.

• As part of the PRA model update in 2009, the gap analysis will be updated to reflect pertinent changes to both the PRA Standard and Regulatory Guide 1.200.

A summary of the disposition of 1998 Industry PRA Peer Review facts and observations (F&Os) for the PBAPS, Units 2 and 3 PRA models was documented as part of the statement of PRA capability for MSPI in the PBAPS MSPI Basis Document [4]. As noted in that document, there were no significance level A F&Os from the peer review, and all significance level B F&Os were addressed and closed out with the completion of the current PB205 and PB305 models of record. Also noted in that submittal was the fact that, after allowing for plant-specific features, there are no MSPI cross-comparison outliers for PBAPS (refer to the third bulleted item above).

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Attachment 2 Response to Request for Supplemental Information Concerning Relief Request 14R-44 A Gap Analysis for the 2002 PBAPS, Units 2 and 3 PRA models (PB202 and PB302, respectively) was completed in January 2004. This Gap Analysis was performed against PRA Standard RA-S-2002 [2] and associated NRC comments in draft regulatory guide DG-1122 [3], the draft version of Regulatory Guide 1.200 Revision O. This gap analysis defined a list of 83 supporting requirements from the Standard for which potential gaps to Capability Category II of the Standard were identified. For each such potential gap, a PRA updating requirements evaluation (URE- EGC model update tracking database) was documented for resolution.

A PRA model update was completed in 2006, resulting in the PB205C and PB305C updated models. In updating the PRA, changes were made to the PRA to address most of the identified gaps, as well as to address other open UREs. Following the update, an assessment of the status of the gap analysis relative to the new model and the updated requirements in Addendum B of the ASME PRA Standard concluded that 59 of the gaps were fully resolved (Le., are no longer gaps), and another seven were partially resolved.

Two additional gaps were identified during the performance of the review based on additional SRs that were added to Addendum B of the PRA standard [5] and NRC issued clarifications [6] after the 2004 gap analysis had been performed. A summary of the current open items including the partially resolved items is provided in attached Table 1.

Of the remaining gaps, those pertaining to the internal flooding analysis and LERF analysis will be addressed during the internal flooding and Level 2 model update that is ongoing in 2008. These analysis updates will be integrated into the Level 1 internal events model update that is scheduled to occur in 2009. The other remaining gaps will be reviewed for consideration during the 2009 model update process but are judged to have low impact on the PRA model or its ability to support a full range of PRA applications. The remaining gaps are documented in the URE database so that they can be tracked and their potential impacts accounted for in applications where appropriate.

General Conclusion Regarding PRA Capability The PBAPS, Units 2 and 3 PRA maintenance and update processes and technical capability evaluations described above provide a robust basis for concluding that the PRA is suitable for use in risk-informed licensing actions. As specific risk-informed PRA applications are performed, remaining gaps to specific requirements in the PRA standard will be reviewed to determine which, if any, would merit application-specific sensitivity studies in the presentation of the application results.

Assessment of PRA Capability Needed for Risk-Informed Inservice Inspection In the risk-informed inservice inspection (RI-ISI) program at PBAPS, the EPRI Risk-informed lSI methodology [7] is used to define alternative inservice inspection requirements. Plant-specific PRA-derived risk significance information is used during 3

Attachment 2 Response to Request for Supp/ementa//nformation Concerning Relief Request /4R-44 the RI-ISI plan development to support the consequence assessment, risk ranking, element selection and delta risk evaluation steps.

The importance of PRA consequence results, and therefore the scope of PRA technical capability, is tempered by three fundamental components of the EPRI methodology.

First, PRA consequence results are binned into one of three conditional core damage probability (CCDP) and conditional large early release probability (CLERP) ranges before any welds are chosen for RI-ISI inspection as illustrated below. Broad ranges are used to define these bins so that the impact of uncertainty is minimized and only substantial PRA changes would be expected to have an impact on the consequence ranking results.

Consequence Results Binning Groups Consequence Category CCDP Range CLERP Range High CCDP> 1E-4 CLERP> 1E-5 Medium 1E-6 < CCDP =s 1E-4 1E-7 < CLERP =s 1E-5 Low CCDP =s 1E-6 CLERP =s 1E-7 The risk importance of a weld is therefore not tied directly to a specific PRA result.

Instead, it depends only on the range in which the PRA result falls. As a consequence, any PRA modeling uncertainties would be mitigated by the wide binning provided in the methodology. Additionally, conservatism in the binning process (e.g., as would typically be introduced through PRA attributes meeting ASME PRA Standard Capability Category I versus II) will tend to result in a larger inspection population.

Secondly, the impacts of particular PRA consequence results are further dampened by the joint consideration of the weld failure potential via a non-PRA-dependent damage mechanism assessment. The results of the consequence assessment and the damage mechanism assessment are combined to determine the risk ranking of each pipe segment (and ultimately each element) according to the EPRI Risk Matrix. The Risk Matrix, which equally takes both assessments into consideration, is reproduced below.

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Attachment 2 Response to Request for Supp/ementa//nformation Concerning Relief Request /4R-44 CONSEQUENCES OF PIPE RUPTURE POTENTIAL FOR IMPACTS ON CONDITIONAL CORE DAMAGE PROBABILITY PIPE RUPTURE AND LARGE EARLY RELEASE PROBABILITY PER DEGRADATION MECHANISM SCREENING CRITERIA NONE LOW MEDIUM HIGH HIGH LOW FLOW ACCELERATED CORROSION Category 7 MEDIUM LOW LOW OTHER DEGRADATION MECHANISMS Category 7 Category 6 LOW LOW LOW LOW NO DEGRADATION MECHANISMS Category 7 Category 7 Category 6 Thirdly, the EPRI RI-ISI methodology uses an absolute risk ranking approach. As such, conservatism in either the consequence assessment or the failure potential assessment will result in a larger inspection population rather than masking other important components. That is, providing more realism into the PRA model (e.g., by meeting higher capability categories) most likely would result in a smaller inspection population.

These three facets of the methodology reduce the importance and influence of PRA on the final list of candidate welds.

The limited manner of PRA involvement in the RI-ISI process is also reflected in the risk-informed license application guidance provided in Regulatory Guide 1.174 [8].

Section 2.2.6 of Regulatory Guide 1.174 provides the following insight into PRA capability requirements for this type of application:

There are, however, some applications that, because of the nature of the proposed change, have a limited impact on risk, and this is reflected in the impact on the elements of the risk model.

An example is risk-informed inservice inspection (RI-ISI). In this application, risk significance was used as one criterion for selecting pipe segments to be periodically examined for cracking. During the staff review it became clear that a high level of emphasis on PRA technical acceptability was not necessary.

Therefore, the staff review of plant-specific RI-ISI typically will include only a limited scope review of PRA technical acceptability.

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Attachment 2 Response to Request for Supplemental Information Concerning Relief Request 14R-44 In addition to the above, it is noted that welds determined to be low risk significant are not eliminated from the lSI program on the basis of risk information. For example, the risk significance of a weld may fall from Medium Risk Ranking to Low Risk Ranking, resulting in it not being a candidate for inspection. However, it remains in the program, and if, in the future, the assessment of its ranking changes (either by damage mechanism or PRA risk) then it may again become a candidate for inspection. If it is discovered during the RI-ISI update process that a weld is now susceptible to flow-accelerated corrosion (FAC), inter-granular stress corrosion cracking (IGSCC), or microbiological induced cracking (MIC) in the absence of any other damage mechanism, then it is addressed in an "augmented" program where it is monitored for those special damage mechanisms. That occurs no matter what the Risk Ranking of the weld is determined to be.

Conclusion Regarding PRA Capability for Risk-Informed lSI The PBAPS, Units 2 and 3 PRA models continue to be suitable for use in the risk-informed inservice inspection application. This conclusion is based on:

• the PRA maintenance and update processes in place,

• the PRA technical capability evaluations that have been performed and are being planned, and

• the RI-ISI process considerations, as noted above, that demonstrate the relatively limited sensitivity of the EPRI RI-ISI process to PRA attribute capability beyond ASME PRA Standard Capability Category I.

As the PRA analyses for the PBAPS, Units 2 and 3 10-year interval evaluation are performed during 2008 using the PB205 and PB305 PRA models, respectively, the remaining gaps to the PRA standard will be reviewed to determine which, if any, would merit RI-ISI-specific sensitivity studies in the presentation of the application results.

References

1. Boiling Water Reactors Owners' Group, BWROG PSA Peer Review Certification Implementation Guidelines, Revision 3, January 1997.

2. American Society of Mechanical Engineers, Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications, ASME RA-S-2002, New York, New York, April 2002.

3. U.S. Nuclear Regulatory Commission, An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities, Draft Regulatory Guide DG-1122, November 2002.

4. Peach Bottom MSPI Basis Document, Rev. 2, March 27,2007.

5. American Society of Mechanical Engineers, Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications, ASME RA-Sb-2005, New York, New York, December 2005.

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Attachment 2 Response to Request for Supplemental Information Concerning Relief Request 14R-44

6. U.S. Nuclear Regulatory Commission Memorandum to Michael T. Lesar from Farouk Eltawila, "Notice of Clarification to Revision 1 of Regulatory Guide 1.200," for publication as a Federal Register Notice, July 27,2007.

7. Revised Risk-Informed Inservice Inspection Evaluation Procedure, EPRI TR-112657, Revision B-A, December 1999.

8. U.S. Nuclear Regulatory Commission, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, Regulatory Guide 1.174, Revision 1, November 2002.

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Attachment 2 Response to Request for Supplemental Information Concerning Relief Request I4R-44 TABLE 1 - Status of Identified Gaps to Capability Category II of the ASME PRA Standard Applicable Current Status / Comment Importance to RI-ISI Title Description of Gap SRs Gap #1 Update the Peach Bottom ISLOCA evaluation IE-C12 Open - ISLOCA update has not Not significant given that the to be consistent with more recent Exelon yet been performed. However, current approach is reasonably evaluations. the current ISLOCA values are conservative.

reasonably conservative compared to other sites that have utilized the more detailed methodology.

Gap #2 Interview plant operations, maintenance, IE-A6 Open - Although this would be None. Category I is met and engineering, and safety analysis personnel for an enhancement to the IE appropriate for this application.

the purpose of identifying potential IEs that Notebook, it is not judged as a may have been overlooked. Alternatively, have high priority. The current IE such personnel review Section 2 of the Peach evaluation provides thorough Bottom PRA IE Notebook and provide documentation of the Initiating comments to this effect. Incorporate results of Events considered in the these interviews/reviews as an appendix to the PBAPS model that is consistent IE Notebook or as a set of appropriate with other BWRs.

sentences (with references) to Section 2 of the IE Notebook. Note that Cat I for this SR does not require the performance of interviews for this purpose.

Gap #6 Development of a Peach Bottom PRA SC-A4 Partially resolved - Although a None. Dependencies are Dependency Matrix Notebook such that it specific dependency matrix modeled. This is simply a becomes the notebook describing the notebook has not been prepared baseline PRA model approach to treatment of all the various type of for Peach Bottom, each of the documentation consideration.

dependencies throughout the PRA should be system notebooks includes a considered. This can be accomplished by description of all dependencies summarizing how all the various aspects of and includes a detailed dependencies are treated and where the dependency matrix.

associated analyses for the dependencies Additionally, accident sequence (e.g., supporting walkdown information, room dependencies as a function of cooling assumptions, water supply duration, initiating event category are HRA, CCF) are documented. discussed in the event tree notebook.

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Attachment 2 Response to Request for Supplemental Information Concerning Relief Request I4R-44 Applicable Current Status / Comment Importance to RI-ISI Title Description of Gap SRs Gap #11 Provide descriptions of the limitations of SC-C2 Open - Included in practice. None. The model is not used thermal hydraulic analyses with respect to their MAAP was not utilized outside beyond its known limitations.

use in the PRA (bases for success criteria, the bounds of known This is a documentation HRA timing, etc.) and ensure the application is acceptability. Otherwise, consideration only.

within the limits of the code. Assessments of awaiting guidance from EPRI the capability limitations may be limited to the and endorsement from NRC.

specific application of the calculation.

Gap #25 To meet the requirements of SR HR-A1 and HR-A1 Open - Pre-initiator errors are Not significant. Capability HR-B1, the following would be developed as HR-B1 included for some risk significant Category I is believed to be met supporting documentation for PBAPS: systems (i.e. HPCI, RCIC, for HR-B1. The pre-initiator

- A list of the PRA systems to consider for test LPCS, and SLCS) on a generic assessment that exists is and maintenance actions basis. adequate for the RI-ISI

- Rules for identifying and screening test and The performance of a detailed application. Pre-initiator human maintenance actions from the PRA process for identifying and actions do not contribute

- A list of procedures reviewed, the potential screening test and maintenance significantly to the risk test and maintenance actions associated with pre-initiators is judged to have a significance results for this the procedures, and the disposition of the minimal impact on the results of application.

action (screened or evaluated). the model.

Gap #26 To meet the requirements of SR HR-A2, the HR-A2 Partially Resolved - The process Not significant. The pre-initiator following would be developed as supporting did not include a procedure assessment that exists is documentation for PBAPS: review but did include a review adequate for the RI-ISI

- A list of the PRA systems to consider for mis- of the need for transmitter/trip application, given the evaluation calibration actions unit components to function that has been performed and

- Rules for identifying and screening mis- properly, or where false signals reflected in the model.

calibration actions from the PRA could prematurely terminate the

- A list of procedures reviewed, the potential system function.

mis-calibration actions associated with the procedures, and the disposition of the action (screened or evaluated).

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Attachment 2 Response to Request for Supplemental Information Concerning Relief Request I4R-44 Applicable Current Status / Comment Importance to RI-ISI Title Description of Gap SRs Gap #27 To meet the requirements of SR HR-A3, the HR-A3 Partially Resolved - The process Not significant. The pre-initiator following would be developed as supporting did not include a procedure assessment that exists is documentation for PBAPS: review but did include a review adequate for the RI-ISI

- A list of the PRA systems to consider for of the need for transmitter/trip application, given the evaluation common cause mis-calibration actions unit components to function that has been performed and

- Rules for identifying and screening common properly, and common cause reflected in the model.

cause mis-calibration actions from the PRA mis-calibrations were also

- A list of procedures reviewed, the potential included.

common cause mis-calibration actions associated with the procedures, and the disposition of the action (screened or evaluated).

Gap #31 Establish the significant pre-initiator HFEs HR-D2 Partially Resolved - Pre- None. The updated PRA model based on the DG-1122 definition, and re- initiators were included in the meets HR-D2 at Capability quantify the balance of the significant HFEs system models as described in Category I, which is sufficient for using the methodologies outlined in PB02AF- the system notebooks that were the RI-ISI application.

003. created as part of the 2005 update. The process included a review of the need for transmitter/trip unit components to function properly, or where false signals could prematurely terminate the system function.

However, not all significant pre-initiators were evaluated with a detailed HEP analysis. Rather, they were assigned a 'type' based on the transmitter it is associated with, and the types were assigned an HEP value based on the limited set of detailed pre-initiator evaluations that were performed as described in the HRA notebook.

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Attachment 2 Response to Request for Supplemental Information Concerning Relief Request I4R-44 Applicable Current Status / Comment Importance to RI-ISI Title Description of Gap SRs Gap #54 Document and employ the methodology used DA-C6 Open - For the most part, the Not significant. The model is for determining the standby component estimated demands were reasonably consistent with data number of demands to include plant specific: determined from the from the plant MR database, a) surveillance tests, b) maintenance acts, c) Maintenance Rule database, but which is adequate for RI-ISI surveillance tests or maintenance on other a confirmation that it is collected application.

components, d) operational demands. exactly consistent with the DA-Additional demands from post-maintenance C6 requirements has not been testing should not be included. performed. This is judged to have a minimal impact on the Bayesian updated reliability values utilized in the model.

Gap #55 To be consistent with SR DA-C8, the Peach DA-C8 Open - Note that Category I None. Capability Category I is Bottom PRA would need to be enhanced to allows for estimates of standby met, which is adequate for RI-include reviews of operating experience to status estimates as an ISI.

determine the times that components were in acceptable approach.

standby.

Gap #58 Ensure that the enhancements associated with DA-C11 Open - The maintenance rule Not significant. The model is DA-C4 include the guidance regarding the data is used directly, but a reasonably consistent with data definition of maintenance hours that is confirmation that it collected from the plant MR database, provided in SR DA-C11 and that the counting exactly consistent with the DA- which is adequate for RI-ISI of unavailability hours follows that definition. C11 requirements has not been application.

performed. This is judged to have a minimal impact on the unavailability hours used in the model.

Gap #59 Ensure that the enhancements associated with DA-C12 Open - The maintenance rule Not significant. The model is DA-C4 include 1) the guidance regarding the data is used directly, but a reasonably consistent with data treatment of maintenance hours vs. plant confirmation that it collected from the plant MR database, operational status that is provided in SR DA- exactly consistent with the DA- which is adequate for RI-ISI C12 (and ensure that the counting of C11 requirements has not been application.

unavailability hours follows that definition); and performed. This is judged to

2) perform interviews of maintenance staff for have a minimal impact on the equipment with incomplete or limited unavailability hours used in the maintenance information. model.

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Attachment 2 Response to Request for Supplemental Information Concerning Relief Request I4R-44 Applicable Current Status / Comment Importance to RI-ISI Title Description of Gap SRs Gap #60 To be consistent with SR DA-C13, the PRA DA-C13 Partially resolved - Model Not significant. The model is should include an examination of coincident includes coincident outage times reasonably consistent with outage times for redundant equipment (both for a few pertinent combinations known plant operating practice intra- and inter-system) and incorporate the (e.g. HPCI/RCIC, RHR Loops), and experience. An exhaustive results into the modeling and documentation. but since no known overlap assessment is not needed to However, it is judged that it is not practical to existed for these combinations, support use of the PRA for RI-model all potential combinations of coincident an arbitrarily small value (1.0E- ISI application.

maintenance unavailability values, and that a 5) was assigned.

review of maintenance experience would not be sufficient to allow the prediction of the It is judged that the dominant risk contributor combinations. As incorporation of coincident such, the approach suggested is to identify maintenance terms will have a dominant risk contributor combinations based minimal impact on the results of on knowledge of the accident sequences the model.

modeling, and model such combinations of coincident maintenance outages in the fault tree logic. A review of recent maintenance experience would then be performed to identify events of coincident maintenance outages for these combinations to support probability estimation for the events.

Gap #65 During the plant specific data update, ensure DA-D7 Partially resolved - The None. The process used is the data used reflects the current design and Component Data Notebook appropriate. This is a operating conditions. Include guidance in the includes development of the documentation issue only.

documentation related to updating data when updated plant-specific data changes are made to equipment or operating evaluation. Specific guidance conditions. on updating data when changes are made is not provided, but providing these definitions should not have an impact on the quantitative results from the PRA model.

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Attachment 2 Response to Request for Supplemental Information Concerning Relief Request I4R-44 Applicable Current Status / Comment Importance to RI-ISI Title Description of Gap SRs Gap #67 The Peach Bottom PRA appropriately includes IF-F* Open - Internal Flood analysis Not applicable. In the PBAPS a number of internal flood initiators and being updated in 2008. RI-ISI process, the internal associated event trees (refer to Section 9 of flooding PRA model was not the main documentation). The internal flooding directly used to support the analysis needs to be expanded into a single development of the ISI program, comprehensive analysis, and updated where and no modifications to the appropriate. Flooding documentation needs to internal flooding portion of the be upgraded especially for walkdowns and PRA model are made in descriptions of calculations supporting the conducting the analysis.

quantitative analysis.

Gap #68 Identify the PRA modeled SSCs in flood areas IF-A* Open - Internal Flood analysis Not applicable. See Gap #67.

per requirements of IF-A2 and IF-A3. being updated in 2008.

Gap #69 Identify and document potential flood sources IF-B* Open - Internal Flood analysis Not applicable. See Gap #67.

for areas that do not screen out per the being updated in 2008.

requirements in IF-B1, B2, B3, and B4.

Gap #70 Identify and document scenarios, propagation IF-C* Open - Internal Flood analysis Not applicable. See Gap #67.

paths, and affected SSCs per the being updated in 2008.

requirements in IF-C1, C2, C3, and C4.

Gap #71 Identify human actions for flood mitigation and IF-C6 Open - Internal Flood analysis Not applicable. See Gap #67.

incorporate into model per IF-C6 standards being updated in 2008.

Gap #72 Review and update flood frequencies per IF- IF-D* Open - Internal Flood analysis Not applicable. See Gap #67.

D2, D3, D4, and D5. being updated in 2008.

Gap #73 Review and develop flood sequences per the IF-E* Open - Internal Flood analysis Not applicable. See Gap #67.

requirements of IF-E1, E2, E3, E4, E5, and E6. being updated in 2008.

Gap #77 The uncertainty analysis could be further QU-E2 Partially resolved - Sensitivity See Add #2.

enhanced by providing a discussion of the studies included as part of the guidelines used to review results and identify evaluation in Section 4.5 of the important contributors to uncertainty. Use of a PB PRA Summary Notebook, systematic process of identifying these areas but the choice of sensitivities and evaluating them may improve the overall could be judged as not a quality of the analysis. systematic process. However, the QU-E2 SR definition has since changed - refer to Add #2 below.

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Attachment 2 Response to Request for Supplemental Information Concerning Relief Request I4R-44 Applicable Current Status / Comment Importance to RI-ISI Title Description of Gap SRs Gap #80 Include an assessment of the significance of QU-F4 Open - Identification of key See Add #2.

assumptions on the quantitative results. assumptions will be application specific. Also, the QU-F4 SR has been redefined.

Gap #83 Strict reading of LE-E4 would indicate that the LE-E4 Open - Level 2 Analysis is being LERF results from the updated following enhancements to the LERF analysis updated in 2008. model will need to be examined and associated documentation would need to to determine if the RI-ISI update be made to comply with the Standard: would be significantly impacted.

- Explicitly assess dependencies among Level 2 HEPs (and combinations of Level 2 HEPs with Level 1 HEPs)

- Perform quantitative sensitivity studies of the LERF analysis- Perform quantitative uncertainty assessment of the LERF analysis.

Add #1 Addendum B of the ASME PRA Standard [5] QU-F6 Open - These new SRs will be None. This is a documentation added SRs to document the quantitative LE-G6 addressed during the next full issue. The model is not being definition used for significant basic event, PRA model update, but changed to address this item.

significant cutset, significant accident providing these definitions sequence, and significant accident progression should not have an impact on sequence in the CDF and LERF analysis. the quantitative results from the PRA model.

Add #2 Several SRs associated with treatment of QU-E1 Open - These recently To be determined once the new model uncertainty and related model QU-E2 redefined SRs will be addressed NRC/EPRI guidance is assumptions have been recently redefined. QU-E4 during the next full PRA model available. However, the EPRI NRC has issued [6] a clarification to its QU-F4 update after the NRC and EPRI RI-ISI process is defined such endorsement of the PRA Standard. NRC and IE-D3 guidance becomes available. that model uncertainties will not EPRI are currently preparing guidance on an AS-C3 unduly influence results.

acceptable process for meeting these SC-C3 requirements. SY-C3 HR-I3 DA-E3 IF-F3 LE-G4 14