Letter Sequence Draft RAI |
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Category:Memoranda
MONTHYEARML23276A6522023-10-11011 October 2023 Pre-submittal Meeting Summary, September 14, 2023 CLI-22-04, Change Letter to Peach Bottom Subsequent Renewed Licenses March 17 2022 Rev 12022-03-25025 March 2022 Change Letter to Peach Bottom Subsequent Renewed Licenses_March 17 2022_Rev 1 ML21309A5482021-11-15015 November 2021 NSIR Staff Review of the Wolf Creek Generating Stations Security Plan Training & Qualification Plan & Safeguards Contingency Plan for the Verification of ASM EA 20 091 Incorporation ML21277A2472021-11-0505 November 2021 Notification of Significant Licensing Action - Proposed Issuance of Order Approving the Transfer of Licenses for Which a Hearing Has Been Requested - Exelon Generation Company, LLC; Et. Al ML21243A4492021-09-0202 September 2021 ISFSI Technical Assistance Request - Review of Physical Security Plan ML20296A3342020-10-21021 October 2020 ISI Remote Inspection - Supplemental Request for Information ML19088A0462019-03-26026 March 2019 Submittal of 2018 Occupational Exposure Report (1O CFR 20.2206(b) ML18288A1942018-10-25025 October 2018 Summary of the Site Visit Related to the Review of the Subsequent License Renewal Application for the Peach Bottom Atomic Power Station Units 2 and 3 ML18151A1632018-06-0404 June 2018 Summary of Peach Bottom Annual Assessment Meeting and Attendee List ML18100A2112018-04-26026 April 2018 Notice of Public Meeting May 24, 2018 ML18044A1632018-02-20020 February 2018 01/18/2018 Summary of Pre-Application Meeting with Exelon Corporation Regarding the Peach Bottom, Units 2 and 3, Subsequent License Renewal Application ML17271A0532017-09-29029 September 2017 2017 Summary of Annual Decommissioning Funding Status Reports for Reactors in Decommissioning ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML17090A1282017-04-0505 April 2017 Notice of Public Meeting with Exelon Generation Company, LLC to Discuss Nrc'S Assessment of Safety Performance at Peach Bottom Atomic Power Station for 2016 ML16221A6802016-08-0808 August 2016 Draft Request for Additional Information ML16209A2042016-07-27027 July 2016 Draft Request for Additional Information ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML16056A5632016-02-25025 February 2016 Draft Request for Additional Information ML15253A5802015-09-0909 September 2015 Draft Request for Additional Information ML15223A5152015-08-10010 August 2015 Draft Request for Additional Information ML15205A3562015-07-24024 July 2015 Draft Request for Additional Information ML15127A2472015-05-0606 May 2015 Draft Request for Additional Information ML15127A5182015-05-0505 May 2015 Draft Request for Additional Information (Tac No. MF4792) ML15110A0602015-04-17017 April 2015 Draft Request for Additional Information ML15098A0392015-04-0808 April 2015 Draft Request for Additional Information ML15078A0832015-03-19019 March 2015 Draft Request for Additional Information (TAC Nos. MF5172 and MF5173) ML15077A2742015-03-18018 March 2015 March 26, 2015, Forthcoming Closed Meeting with Exelon Generation Company, LLC, (Exelon) to Discuss Steam Dryer Analysis Methodology Change for Peach Bottom Atomic Power Station (Pbaps), Unit 2 ML15056A0462015-02-24024 February 2015 Draft Request for Additional Information ML14349A7072014-12-12012 December 2014 Draft Request for Additional Information ML14309A7732014-11-0404 November 2014 Draft Request for Additional Information ML14133A0592014-07-0101 July 2014 Summary of Closed Meeting Between Representatives of the Army Corps of Engineers, Nuclear Regulatory Commission, Federal Energy Regulatory Commission, Exelon Generation Co, LLC, and PPL Susquehanna, LLC, to Discuss Dam Failure Analysis.. ML14112A2392014-04-22022 April 2014 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Peach Bottom Atomic Power Station Units 2 and 3, Susquehanna Steam Electric Station Units 1 and 2, and Three Mile Island Nuclear Station Unit 1 ML14063A3862014-03-0606 March 2014 Notice of Forthcoming Closed Meeting with Exelon Generation Company, LLC (Exelon) to Discuss Steam Dryer Analysis Related to Proposed Extended Power Uprate (EPU) for Peach Bottom Atomic Power Station (Pbaps), Unit Nos. 2 and 3 ML14056A1152014-02-24024 February 2014 Draft Request for Additional Information ML13309A0802013-12-11011 December 2013 Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors ML13338A2502013-12-0404 December 2013 Notice of Forthcoming Closed Meeting with Exelon Generation Company, LLC (Exelon) to Discuss Steam Dryer Analysis Related to Proposed Extended Power Uprate (EPU) for Peach Bottom Atomic Power Station (Pbaps), Units 2 and 3 ML13261A1572013-09-17017 September 2013 Draft Request for Additional Information ML13190A3522013-07-10010 July 2013 Notice of Forthcoming Teleconference with Exelon Generation Company, LLC ML13154A2762013-03-0606 March 2013 NRC Comments on Draft Licensee-Developed Exam (Operating) (Folder 2) ML13063A3372013-03-0404 March 2013 Draft Request for Additional Information ML12348A6962012-12-17017 December 2012 1/3/2013 - Notice of Forthcoming Meeting with Exelon Generation Company, LLC, to Discuss Requests for Additional Information Regarding Exelon Physical Security Plans ML12310A4882012-11-0505 November 2012 Draft Request for Additional Information ML12236A1542012-08-22022 August 2012 Draft Request for Additional Information ML12194A6082012-07-12012 July 2012 Draft Request for Additional Information ML12137A1792012-05-17017 May 2012 Forthcoming Pre-submittal Public Meeting with Exelon Generation Company, LLC Regarding LaSalle Extended Power Uprate Replacement Steam Dryer ML1208602902012-03-26026 March 2012 Notice of Forthcoming Public Meeting with Exelon Generation to Discuss Future Fleet Submittal Regarding Licensed Operator Eligibility Requirements ML1206600702012-03-0606 March 2012 02/21-22/2012 Meeting Summary with State-Of-The-Art Reactor Consequence Analyses (Soarca) for Public Meetings at Peach Bottom and Surry ML11250A1712011-09-14014 September 2011 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs) 2023-10-11
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARIR 05000277/20244012023-10-0505 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000277/2024401 and 05000278/2024401 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML22118A3312022-04-28028 April 2022 NRR E-mail Capture - Peach Bottom - Formal RAI for Proposed Alternative I5R-14, Revision 1 ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22021A5692022-01-21021 January 2022 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000277/2022403 and 05000278/2022403 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21035A2222021-02-0404 February 2021 Notification of Conduct of a Fire Protection Team Inspection ML21091A1782021-02-0202 February 2021 Ti 2515/194 Inspection Documentation Request ML21012A1302021-01-12012 January 2021 Request for Additional Information - TSTF-505 ML20357A0972020-12-21021 December 2020 Request for Additional Information - TSTF-505 ML20296A3342020-10-21021 October 2020 ISI Remote Inspection - Supplemental Request for Information ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval ML20070R2282020-03-10010 March 2020 Request for Additional Information - RR ML19303D1662019-10-31031 October 2019 Requests for Additional Information for the Environmental Review of the Peach Bottom Subsequent License Renewal Application - Set 2 (EPID No. L-2018-RNW-0013)- RAIs ML19232A1752019-08-20020 August 2019 Request for Additional Information - TSTF-500 Implementation LAR ML19140A2832019-05-15015 May 2019 Email - Peach Bottom Atomic Power Station, Units 2 and 3 Second Round RAI Request - Set 1 ML19140A2822019-05-15015 May 2019 027 Pb FU RAI Subsequent to Clarification Call - Cu Greater than 15 Zn Holston (Jg) ML19253D2932019-05-0707 May 2019 002 Attachment 4D Confirmation Water Chemistry Chereskin Revised (002) ML19249C7252019-05-0303 May 2019 SLRA Requests for Additional Information - Set 2 May 3, 2019 ML19108A4282019-04-10010 April 2019 RAIs SLRA Set 1_ERO(Rev 1) ML19079A0232019-03-19019 March 2019 Licensed Operator Positive Fitness-For-Duty Test ML19058A2902019-02-27027 February 2019 Request for Additional Information - High Pressure Service Water One Time TS Change ML19037A4832019-02-0606 February 2019 NRR E-mail Capture - Clarification Questions Associated with Staff Assessment of Peach Bottom Seismic Probabilistic Risk Assessment Report Dated August 28, 2018 ML19028A0062019-01-25025 January 2019 Secondary Containment LAR Requests for Additional Information ML19017A0472019-01-16016 January 2019 Request for Additional Information - High Pressure Service Water One Time TS Change ML18348B0292018-12-13013 December 2018 Subsequent License Renewal Severe Accident Mitigation Alternatives Requests for Additional Information ML19010A3832018-12-0707 December 2018 Additional Documents Needed for Peach Bottom SLR Environmental Review ML18324A6742018-11-15015 November 2018 Request for Additional Information (FINAL)- LAR to Allow 2SRV/SVs OOS at High Pressure ML18312A4072018-11-0808 November 2018 Request for Additional Information (Public) - LAR to Allow 2SRV/SVs OOS at High Pressure ML18276A0202018-10-0202 October 2018 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan for Limerick and Peach Bottom ML18240A1742018-08-28028 August 2018 Request for Additional Information (Final) - Adopt TSTF-500 Battery TS Changes LAR ML18239A1322018-08-27027 August 2018 Request for Additional Information Final - Relief Request I5R-04 ML18228A6762018-08-14014 August 2018 Request for Additional Information - Adopt TSTF-500 Battery TS Changes LAR ML18226A2012018-08-14014 August 2018 Request for Additional Information - Relief Request I5R-05 ML18214A2812018-08-0202 August 2018 Request for Additional Information Draft - Relief Request I5R-02 ML18200A2742018-07-17017 July 2018 Request for Additional Information 2nd Round (Final) - Adopt 50.69 License Amendment ML18192A1192018-07-10010 July 2018 Request for Additional Information 2nd Round (Final) - Adopt 50.69 License Amendment ML18178A4772018-06-27027 June 2018 Request for Additional Information 2nd Round - Adopt 50.69 License Amendment ML18096B5062018-04-0606 April 2018 Request for Additional Information Exelon Generation Company, LLC Requested Amendment to Adopt 10 CFR 50.69 for Risk-informed Categorization and Treatment of Structures, Systems and Components ML18094B0832018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29) ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML17317B5502017-11-0909 November 2017 Licensed Operator Positive Fitness-For-Duty Test ML17240A0062017-08-24024 August 2017 Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML17222A0962017-08-10010 August 2017 Request for Additional Information - Amendment Request Regarding Safety Relief Valve and Safety Valce Operability for Cycle 22 2023-09-21
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 19, 2015 MEMORANDUM TO: Douglas A. Broaddus, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS.
MF5172 AND MF5173)
The attached draft request for additional information (RAI) was transmitted on March 18, 2015, to Mr. Tom Loomis of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees amendment request for Peach Bottom Atomic Power Station, Units 2 and 3, dated November 7, 2014. The proposed amendment would revise the Technical Specifications (TSs) associated with the primary containment leakage rate testing program. Specifically, the amendment would extend the frequencies for performance of the Type A containment integrated leakage rate test (ILRT) and the Type C containment isolation valve leakage rate test, required by 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.
The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.
Docket Nos. 50-277 and 50-278
Attachment:
Draft RAI
MEMORANDUM TO: Douglas A. Broaddus, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS.
MF5172 AND MF5173)
The attached draft request for additional information (RAI) was transmitted on March 18, 2015, to Mr. Tom Loomis of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees amendment request for Peach Bottom Atomic Power Station, Units 2 and 3, dated November 7, 2014. The proposed amendment would revise the Technical Specifications (TSs) associated with the primary containment leakage rate testing program. Specifically, the amendment would extend the frequencies for performance of the Type A containment integrated leakage rate test (ILRT) and the Type C containment isolation valve leakage rate test, required by 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.
The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.
Docket Nos. 50-277 and 50-278
Attachment:
Draft RAI DISTRIBUTION PUBLIC FFarzam, NRR/DE/EMCB LPL1-2 R/F THilsmeier, NRR/DRA/APLA RidsNrrDorlLpl1-2 Resource DWoodyatt, NRR/DSS/SCVB RidsNrrDorlDpr Resource RidsNrrPMPeachBottom Resource ACCESSION NO.: ML15078A083 OFFICE LPL1-2/PM NAME REnnis DATE 03/19/2015 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT PRIMARY CONTAINMENT LEAKAGE RATE TESTING PROGRAM EXELON GENERATION COMPANY, LLC PEACH BOTTOM ATOMIC POWER STATION - UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 By letter dated November 7, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14315A084), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed amendment would revise the Technical Specifications (TSs) associated with the primary containment leakage rate testing program. Specifically, the amendment would extend the frequencies for performance of the Type A containment integrated leakage rate test (ILRT) and the Type C containment isolation valve leakage rate test, required by 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal.
PRA Licensing Branch (APLA)
Reviewer: Todd Hilsmeier APLA-RAI-1 Section 4.2.7 of EPRI TR-1009325, Revision 2-A states that [w]here possible, the analysis should include a quantitative assessment of the contribution of external events (for example, fire and seismic) in the risk impact assessment for extended ILRT intervals. EPRI TR-1009325, Revision 2-A further states that the assessment can be taken from existing, previously submitted and approved analyses or another alternate method of assessing an order of magnitude estimate for contribution of the external event to the impact of the changed interval.
Section 5.7.1 in Attachment 3 of the license amendment request (LAR) assesses the fire risk and states that the reported fire PRA CDF value is 4.4E-5/yr or approximately a factor of 11.9 higher than the current internal events CDF values. Section 5.7.1 further states that a better estimate of the LERF from scenarios more applicable to the fire PRA results would be about 43% [ATWS scenarios contribute 23.0% to the LERF total and ISLOCA scenarios contribute 19.7% to the LERF total] less than the total internal events value of 4.74E-7/yr, or 2.72E-07/yr.
If the multiplier of 11.9 is used on this LERF value, then the total LERF estimate for the Fire PRA model is 3.22E-06/yr. The licensees approach to estimate the total LERF due to fire is the same as the following:
- 1) Multiplying the fire PRA CDF (i.e., 4.4E-5/yr) by a conditional containment failure probability (CCFP) representative of the fire scenarios.
- 2) The CCFP is equal to the internal events LERF (excluding ATWS and ISLOCA scenarios) (i.e., 2.72E-07/yr) divided by the total internal events CDF (which includes the ATWS and ISLOCA scenarios) (i.e., 3.69E-6/yr). In this case the CCFP would be about 0.073.
However, the associated CCFP in the licensees approach does not seem to be appropriate in that if the ATWS/ISLOCA scenarios are excluded in the numerator of CCFP, then the same scenarios should be excluded from the denominator of CCFP. By including the ATWS/ISLOCA scenarios in the denominator of CCFP, the CCFP is artificially reduced, resulting in an underestimation of total fire LERF. If the ATWS/ISLOCA scenarios were excluded from the denominator of CCFP, then the increase in CCFP could potentially, considering ATWSs significant contribution to CDF in NUREG-1150, cause total LERF in Table 5.7-4 in Attachment 3 of the LAR to exceed the Regulatory Guide 1.174 criterion of less than 1.0E-5/yr. This issue is also applicable to the calculation of the seismic LERF in Section 5.7.2 in Attachment 3 of the LAR. Considering the NRC staff comments above, justify that the total LERF in Table 5.7-4 in of the LAR is less than the Regulatory Guide 1.174 criterion of 1.0E-5/yr for total LERF due to internal and external events.
APLA-RAI-2 Section 4.4 in Attachment 3 of the LAR uses the Calvert Cliffs Nuclear Power Plant methodology in evaluating the impact of liner corrosion on the extension of ILRT testing intervals. In addition to the two observed corrosion events at North Anna Power Station, Unit 2 and Brunswick Steam Electric Plant, Unit 2, the licensee identifies two more events that have occurred in recent years (based on a data search covering approximately nine years documented in Reference [21]). It is not clear what date range the nine year data search covers, because Reference 21 in Section 8.0 of Attachment 3 of the LAR seems to be incorrect as it refers to the Individual Plant Examination for External Events dated May 1996. Regarding the data search covering approximately 9 years, please list the correct reference for this report and provide the date range of the data search. Also, indicate if there have been any additional instances of liner corrosion since this data search that could be relevant to this assessment, and, if so, describe its impact on the LAR risk results.
Mechanical and Civil Engineering Branch (EMCB)
Reviewer: Farhad Farzam EMCB-RAI-1 Please discuss the highlights of IWE inspections of the accessible surface areas of the PBAPS Units 2 and 3 containments, performed after the last Type A test, and any corrective action taken to disposition the findings.
EMCB-RAI-2 As stated in the LAR, the PBAPS in-service inspection programs contain requirements to evaluate the acceptability of the inaccessible areas, if such conditions were identified, in accordance with 10 CFR 50.55a(b)(2)(ix)(A).
Please provide information of instances, during implementation of the PBAPS in service inspection programs, where existence of or potential for degraded conditions in inaccessible areas were identified and evaluated based on conditions found in accessible areas, as required by 10 CFR 50.55a(b)(2)(ix)(A). If there were any instances of such conditions, discuss the findings and corrective actions taken to disposition the findings. Also, please identify the specific areas of the PBAPS Units 2 and 3 containments that are inaccessible and susceptible to degradation.
EMCB-RAI-3 It is stated in the LAR that in the second containment in-service inspection interval, the wetted and submerged suppression chamber (torus) surface areas are designated as augmented examination areas and will require 100 percent visual examination during each inspection period. It is also stated that the torus submerged areas were coated in 2012 for Unit 2 and 2013 for Unit 3 in order to arrest further pitting. Please provide the results of recent inspections of the torus and discuss any corrective action taken to disposition the findings.
EMCB-RAI-4 Please provide PBAPS operating experience relative to the inspection of the drywell internal moisture barrier at the juncture of the containment wall and the concrete floor.
EMCB-RAI-5 PBAPS Updated Final Safety Analysis Report (UFSAR), Section 12.2.1 states that (1) the foundation of the reactor building consists of a monolithic concrete mat supported on sound rock; and (2) this foundation mat also supports the primary containment and its internals, including the reactor vessel pedestal.
PBAPS UFSAR, Appendix Q, Section Q.1.16, states that the PBAPS structural monitoring program complies with 10 CFR 50.65 and utilizes visual inspections in managing aging effects for concrete and grout in accessible areas. Please provide PBAPS operating experience, including inspection intervals, relative to the inspection of concrete components, and any corrective action taken to disposition the findings. Also, please discuss whether existence of or
potential for degraded conditions in inaccessible concrete areas were identified and evaluated based on conditions found in accessible areas.
EMCB-RAI-6 Section 9.2.3.2 of NEI 94-01, Revision 2-A, and Condition 2 in Section 4.1 of the NRC safety evaluation for topical report NEI 94-01, Revision 2 require supplemental general visual inspections of accessible interior and exterior surfaces of the containment for structural deterioration that may affect the containment leak-tight integrity. These inspections must be conducted prior to each Type A test and during at least three other outages before the next Type A test if the interval for the Type A test has been extended to 15 years.
Based on the information provided in the LAR, the last Unit 3 Type A test was performed in October 2005, and the upcoming Unit 2 Type A test will be performed no later than October 2015. Please provide a schedule for a typical 15 year interval (between the last Type A test and the proposed next Type A test), in a tabular format, of the in service inspections of PBAPS Units 2 and 3 containments that were, and will be performed, and explain how it meets the requirements in Section 9.2.3.2 of NEI 94 01, Revision 2-A, and Condition 2 in Section 4.1 of the NRC safety evaluation for topical report NEI 94-01, Revision 2.
EMCB-RAI-7 Section 3.4.1 of the LAR discusses PBAPS safety related coating inspection program. Please discuss the highlights of findings from PBAPS recent inspections of the primary containment protective coating and any actions taken to disposition them.
EMCB-RAI-8 Please provide the following information:
a) Percent of the total number of Type B tested components that are on a 120-month extended performance-based test interval.
b) Percent of the total number of Type C tested components that are on a 60 month extended performance-based test interval.