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Category:Letter
MONTHYEARML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks ML23235A0602023-07-17017 July 2023 LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23194A0442023-07-11011 July 2023 Clarification for Indian Point Energy Center License Amendment Request, Independent Spent Fuel Storage Installation Physical Security Plan ML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23171B0432023-06-23023 June 2023 Letter - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML23118A0972023-06-0606 June 2023 06-06-23 Letter to the Honorable Michael V. Lawler, Et Al., from Chair Hanson Regarding Holtec'S Announcement to Expedite Plans to Release Over 500,000 Gallons of Radioactive Wastewater from Indian Point Energy Center Into the Hudson River ML23144A3512023-05-25025 May 2023 Clementina Bartolotta of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3522023-05-25025 May 2023 Loredana Bidmead of New York E-Mail Against Treated Water Release from Indian Point Site ML23144A3412023-05-25025 May 2023 Dianne Schirripa of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23144A3472023-05-25025 May 2023 David Mart of Blauvelt, New York Email Against Treated Water Release from Indian Point Site ML23144A3402023-05-25025 May 2023 Melvin Israel of New York Email Against Treated Water Release from Indian Point Site ML23144A3542023-05-25025 May 2023 Terri Thal of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3532023-05-25025 May 2023 John Shaw of New York Email Against Treated Water Release from Indian Point Site 2024-01-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23171B0442023-06-23023 June 2023 Enclosure - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML22292A2402022-10-21021 October 2022 RAIs for Master Dtf Agreement on IP1 IP2 10 18 2022 ML22103A2442022-04-13013 April 2022 Attachment - Request for Additional Information - License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme for Permanently Defueled Condition for Indian Point Energy Center ML22104A0352022-04-13013 April 2022 Request for Additional Information Related to Exemption Request from Emergency Planning Holtec Decommissioning International, LLC Indian Point Energy Center ML22006A0452022-01-0505 January 2022 PSDAR RAIs Final ML21337A2952021-12-0303 December 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (E-mail Dated 12/3/2021) ML21183A1602021-06-30030 June 2021 Update Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (06/30/2021 E-mail) ML21138A9412021-05-18018 May 2021 Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (05/18/2021 E-mail) ML21112A2672021-04-22022 April 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (Public Redacted Version) ML21019A5672021-01-19019 January 2021 Second Round Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML21013A0152021-01-12012 January 2021 Draft Request for Additional Information (E-mail Dated 1/12/2021) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20268C2352020-09-24024 September 2020 Request for Additional Information (E-mail Dated 9/24/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20233B0152020-08-20020 August 2020 Request for Additional Information (E-mail Dated 8/20/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20190A2342020-07-0808 July 2020 Request for Additional Information - Application for Order Consenting to Transfers of Control of Licenses (07/08/2020 E-mail) ML20190A1502020-06-25025 June 2020 (06/25/2020 E-mail) Draft Request for Additional Information Application for Order Consenting to Transfers of Control of Licenses ML20106F2492020-04-15015 April 2020 E-mail (04/15/2020) Request for Additional Information Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic ML20070J7902020-03-10010 March 2020 Request for Information to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000286/2020012 ML19045A6252019-02-14014 February 2019 Request for Additional Information - Proposed License Amendment Request Regarding Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool - 2/14/19 E-mail from R.Guzman to M.Mirzai NL-18-053, Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension2018-07-18018 July 2018 Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension ML18155A4842018-06-0404 June 2018 Request for Additional Information Regarding Relief Request IP3-ISI-RR-11, E-mail from R.Guzman to C.Mackaman ML18143B6792018-05-23023 May 2018 Request for Additional Information Regarding LAR for One-Time Extension of the Containment Leakage Rate Test - Email from R.Guzman to M.Mirzai ML18094B0922018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59) ML17296A2352017-10-23023 October 2017 Request for Additional Information -10/23/17 E-mail from R.Guzman to R.Louie Cyber Security Plan Milestone 8 Implementation Schedule (CAC Nos. MF9656, MF9657, MF9658; EPID: L-2017-LLA-0217) ML17277B5482017-10-0303 October 2017 Request for Additional Information - Relief Request IP2-ISI-RR-20 Regarding Weld Examination ML17219A1062017-08-10010 August 2017 Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel - Shielded Transfer Canister Requests for Additional Information ML17200A0852017-07-19019 July 2017 Request for Additional Information Regarding the Connection of Non-Seismic Boric Acid Recovery System to RWST Seismic Piping ML17197A0002017-07-17017 July 2017 Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel ML17170A2862017-06-27027 June 2017 RAI Set 2017-06 ML17103A4182017-04-25025 April 2017 Baffle Bolt Rais. Requests for Additional Information for the Review of the Indian Point License Renewal Application (TAC Nos. MD5407 and MD5408) ML17088A4052017-04-20020 April 2017 Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-3 (CAC Nos. MD5407 and MD5408) ML17088A3272017-04-19019 April 2017 Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408) ML17100A1282017-04-11011 April 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment of Inter Unit Transfer of Spent Fuel ML17046A2312017-03-0808 March 2017 Request for Additional Information for the Review of the Indian Point License Renewal - Set 2017-01 ML16232A1192016-09-12012 September 2016 Request for Additional Information for the Review of the Indian Point Nuclear Generating Units Nos. 2 and 3, License Renewal Application Environmental Review - Severe Accident Mitigation Alternatives (CAC Nos. MD5411 and MD5412) ML16138A1942016-07-25025 July 2016 Request for Additional Information for the Review of License Renewal Application, Set 2016-01 ML16139A0302016-06-10010 June 2016 Request for Additional Information Regarding Conditional Exemption from End-of-Line Moderator Temperature Coefficient Measurement ML16112A2262016-04-26026 April 2016 Request for Additional Information Regarding Relief Request IP2-ISI-RR-02 Alternative Examination Volume Required by Code Case N-729-1 ML16041A5782016-02-18018 February 2016 Request for Additional Information Related to License Amendment Request Regarding Moderator Temperature Coefficient Measurement Change ML16005A6292016-01-14014 January 2016 Request for Additional Information Regarding Relief Request IP2-RR-19 ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML15148A4032015-06-29029 June 2015 Request for Additional Information Regarding the Spent Fuel Pool Criticality Analysis ML15156B2742015-06-16016 June 2015 Request for Additional Information Regarding Request to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test ML15125A0972015-05-0606 May 2015 Request for Additional Information Regarding License Amendment to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test ML15071A1012015-05-0404 May 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-01 (TAC Nos. MD5407 and MD5408) ML15103A2592015-04-28028 April 2015 Request for Additional Information Regarding the Proposed License Amendment to Extend the Containment Type a Leak Rate Testing Frequency to 15 Years ML15104A5412015-04-22022 April 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412) ML15072A4172015-03-17017 March 2015 Request for Additional Information Regarding Extension of the Containment Type a Leak Rate Testing Frequency to 15 Years ML14329B2452015-02-18018 February 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Units 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412) CNRO-2015-00008, Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company2015-02-18018 February 2015 Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company 2023-06-23
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 28, 2015 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOSED LICENSE AMENDMENT TO PERMANENTLY EXTEND THE CONTAINMENT TYPE A LEAK RATE TEST FREQUENCY TO 15 YEARS (TAC NO. MF5382)
Dear Sir or Madam:
By letter dated December 9, 2014, Entergy Nuclear Operations, Inc., submitted a license amendment request that would revise Technical Specification 5.5.14 for Indian Point Nuclear Generating Unit No. 2 in order to change the frequency of the Type A, or the containment integrated leak rate test, from once every 10 years to once every 15 years on a permanent basis.
The U.S. Nuclear Regulatory Commission staff has reviewed the submittal and determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Based on our discussions, we understand that a response to the RAI will be provided within 30 days of the date of this letter.
If you have any questions, please contact me at (301) 415-1364 or Douglas.Pickett@nrc.gov.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION PERMANENT EXTENSION OF THE TYPE A LEAK RATE TEST TO 15 YEARS ENTERGY NUCLEAR OPERATIONS. INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247 CONTAINMENT AND VENTILATION BRANCH (SCVB)
SCVB RAl-1 License Amendment Request (LAR) Section 4.3.1, "ILRT [Integrated Leak Rate Test] Results" (Attachment 1, pages 5 and 6 of 19 (Reference 1)), details all test pressures in the absolute pressure scale of "psia" [pounds per square inch absolute]. Without providing the corresponding atmospheric pressure for each test pressure, the U.S. Nuclear Regulatory Commission (NRC) staff cannot confirm that the "calculated peak containment internal pressure for the design basis loss of coolant accident, Pa .... "of 47 psig [pounds per square inch gauge]
was satisfied during ILRT performance (Reference Indian Point Nuclear Generating Unit No. 2 (IP2) Technical Specification (TS) 5.5.14.b), consistent with the direction of Nuclear Energy Institute (NEI) 94-01, Revision 2-A (Reference 2) and the test methodology of American National Standards Institute/American Nuclear Society (ANSI/ANS) 56.8-2002 (Reference 3).
For example, an excerpt from Section 4.3.1 reads:
The last two tests were:
- 1. The last ILRT in April 2006 had a measured containment leak rate (Um) at the test pressure of 60.5 psia was 0.0636% containment air weight/day with a 95% confidence level.
Since Pa equals 47 psig, a test pressure of 60.5 psia prompts concern that the test pressure was not greater than Pa*
The NRC staff requests that the licensee provide the corresponding recorded atmospheric pressures from each of the five ILRT results recorded in Section 4.3.1.
SCVB RAl-2 The last sentence of Attachment 1, page 6 of 19 (Reference 1) from LAR Section 4.3.2, "Type B and C testing," reads, "Notes are provided for test failures." However, no notes in Table 4.3-2 or subsequent pages of the LAR were provided that detail (a) which Type B and Type C local leak rate tests (LLRTs) failed, (b) what corrective actions were performed, and (c) what historical test Enclosure
failures have been repetitive from the total population of Type B penetrations and Type C isolation valves.
The NRC staff requests that the licensee provide this missing information.
SCVB RAl-3 The NRC staff notes that the use of NEI 94-01, Revision 2-A (Reference 2) is acceptable for referencing by licensees proposing to amend their TSs to permanently extend the ILRT surveillance interval to 15 years, provided six specific conditions are satisfied.
Condition 1 from Section 4.1 of NEI 94-01, Revision 2-A reads:
For calculating the Type A leakage rate, the licensee should use the definition in the NEI TR 94-01, Revision 2, in lieu of that in ANSl/ANS-56.8-2002. (Refer to SE [Safety Evaluation] Section 3.1.1.1.).
Section 5.0 of the SE for NEI 94-01, Revision 2-A, reads:
The performance leakage rate is calculated as the sum of the Type A upper confidence limit (UCL) and as-left minimum pathway leakage rate (MNPLR) leakage rate for all Type B and Type C pathways that were in service, isolated, or not lined up in their test position (i.e., drained and vented to containment atmosphere) prior to performing the Type A test. In addition, leakage pathways that were isolated during performance of the test because of excessive leakage must be factored into the performance determination. The performance criterion for Type A tests is a performance leak rate of less than 1.0 La.
Section 3.2.9, "Type A test performance criterion," of ANSl/ANS-56.8-2002 (Reference 3) defines the "performance leakage rate" and reads, in part:
The performance criterion for a Type A test is met if the performance leakage rate is less than La. The performance leakage rate is equal to the sum of the measured Type A test UCL and the total as-left MNPLR of all Type B or Type C pathways isolated during performance of the Type A test. , page 4 of 19 of Entergy's LAR (Reference 1) for IP2 compliance with Condition 1 reads:
Implementation of NEI 94-01 Rev 2A will require use of the definition of "performance leakage rate" defined in Section 5.0 for calculating the Type A leakage rate when performing Type A tests.
The NRC staff notes that the "As found Leakage" is on a continuous trend towards eclipsing the IP2 TS 5.5.14.d.1 leakage rate acceptance criteria of less than or equal to (:s;) 0.75 La (i.e., 0.075 percent containment weight per day) as reflected in SCVB RAl-4 (below). The staff needs to develop a better understanding of why this phenomenon is occurring to make its regulatory decision. The staff notes that IP2's statement of compliance indicates future tense (i.e., "will
require"). To make its regulatory decision, the staff needs to understand whether IP2's Type A ILRT plant test procedures currently reflect the NEI 94-01, Revision 2-A definition of "performance leakage rate." If the IRLT test procedures currently reflect the requisite definition, the staff requests historical information as to when the requisite NEI 94-01, Revision 2-A, definition was adopted into IRLT test procedures. In addition, the staff requests that Entergy Nuclear Operations, Inc. (Entergy), provide a copy of the current IP2 IRLT test procedures, plant drawings, etc. (or procedural excerpts from these documents), to aid the staff in understanding why this phenomenon is occurring, SCVB RAl-4 LAR Section 4.3.1, "ILRT Test Results" (Attachment 1, pages 5 and 6 of 19 (Reference 1))
summarizes the IP2 Type A ILRT test results since August 1979. These test results are summarized in the following table:
Date As found Leakage Test Pressure (psia)
(Percent Containment weight per day)
April 2006 0.0636 60.5 June 1991 0.0478 61.7 December 1987 0.0342 62.9 September 1984 0.0320 65.6 August 1979 0.0260 62.7 The NRC staff notes that the historical trend indicates that consistently, for all five historical ILRTs, the "As found Leakage" is on a continuous trend towards eclipsing the IP2 TS 5.5.14.d.1 leakage rate acceptance criteria of s 0.75 La (i.e., 0.075 percent containment weight per day).
Given the above ILRT results trend, the NRC staff requests that:
(1) The licensee explain why this phenomenon is occurring at IP2. More importantly, what is IP2's long-term corrective action plan to arrest or reverse this trend?
(2) Entergy should include in its response a discussion of any IP2 containment modifications (major or minor) that may have affected containment integrity since August 1979.
(3) For each ILRT, the licensee provide the individual cumulative MNPLR leakage rate for all Type B and Type C pathway test values that constitute a part of the total performance leakage rate (i.e., "As found Leakage") values identified in the table above.
(4) Additional information about how IP2 plant programs satisfy the guidance of Regulatory Position 3, "Element 3: Define Implementation and Monitoring Program," of Regulatory Guide (RG) 1.174, Revision 2 (Reference 4 ).
REFERENCES:
- 1. Letter NL-14-128, dated December 9, 2014, from Lawrence Coyle, Entergy Nuclear Operations to U.S. Nuclear Regulatory Commission regarding the Proposed License Amendment Regarding Extending the Containment Type A Leak Rate Testing Frequency to 15 Years (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14353A015).
- 2. NEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," October 2008 (ADAMS Acces.sion No. ML100620847).
- 3. ANSl/ANS-56.8-2002, Reaffirmed August 9, 2011, "Containment System Leakage Testing Requirements."
- 4. RG 1.174, Revision 2, dated May, 2011, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis" (ADAMS Accession No. ML100910006).
ML15103A259 OFFICE LPL 1-1/PM LPL 1-1/PM LPL2-2/LAiT LPL2-2/LA SC VB/BC LPL 1-1/BC (A)
NAME AGilbertson DPickett LRonewicz KGoldstein RDennig by MDudek (BClayton for) email dated DATE 4/13/2015 4/24/2015 4/20/2015 4/21/2015 3/30/2015 4/28/2015