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Category:E-Mail
MONTHYEARML24032A2442024-02-0101 February 2024 OEDO-24-00011 - 10 CFR 2.206 Petition Holtec Misuse Decommissioning Fund- Email to Petitioner ML24005A1262024-01-0505 January 2024 Permanently Defueled Emergency Plan Implementation Notification ML23055A1532023-02-24024 February 2023 Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22343A2282022-12-0909 December 2022 Acceptance Review: Palisades Proposed Exemption from 10 CFR 50.54(w)(1) - Onsite Property Damage Insurance ML22343A1902022-12-0909 December 2022 Acceptance Review: Palisades Proposed Exemption from 10 CFR 140.11 (a)(4) Primary and Secondary Liability Insurance ML22284A0502022-10-0707 October 2022 Acceptance Review: License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML22227A0082022-08-12012 August 2022 Acceptance Review: Exemption Request from 10CFR50.47(b), 10 CFR 50.47(c)(2), and 10 CFR Part 50, Appendix E, Section IV ML22227A0092022-08-12012 August 2022 Acceptance Review: License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme (L-2022-LLA-0099) ML22179A0752022-06-28028 June 2022 E-mail from Entergy Dated June 28, 2022, Notification of Palisades and Big Rock Point License Transfer (EPIDs L-2022-LLM-0002 and L-2020-LLM-0003) ML22159A2672022-06-0202 June 2022 Answers to Your Questions on Palisades ML22159A2652022-05-0303 May 2022 Questions Asked at Palisades Plant Performance Public Meeting April 26, 2022 ML21328A0062021-11-18018 November 2021 NRR E-mail Capture - (External_Sender) State of Michigan Response - Palisades Nuclear Plant and Big Rock Point Plant - Application for Order Consenting to Transfers of Licenses and Conforming License Amendments ML22208A1052021-11-16016 November 2021 NRR E-mail Capture - (External_Sender) State of Michigan Response - Palisades - Preparation for Issuance of Final Environmental Assessment and Finding of No Significant Impact Holtec Exemption Request to Use Dtf ML21309A5152021-11-0505 November 2021 NRR E-mail Capture - Palisades Nuclear Plant - Preparation for Issuance of Final Environmental Assessment and Finding of No Significant Impact Holtec Exemption Request to Use Dtf ML21309A2982021-11-0505 November 2021 NRR E-mail Capture - Palisades Nuclear Plant and Big Rock Point Plant - Application for Order Consenting to Transfers of Licenses and Conforming License Amendments ML21209A9802021-07-28028 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Rescission of Interim Compensatory Measure from Order EA-02-026 ML21189A2462021-07-0606 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Proposed Partial Exemption from Record Retention Requirements ML21189A0432021-07-0606 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Permanently Defueled Technical Specifications ML21054A1822021-02-23023 February 2021 NRR E-mail Capture - Regarding Public Comment on Palisades Request for Relief RR 5-8 ML21028A4092021-01-27027 January 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Holtec Exemption Request from 10CFR50.82(a)(8)(i)(A) and 10CFR50.75(h)(1)(iv) ML21028A0552021-01-27027 January 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of License Transfer Application ML21007A3752021-01-0707 January 2021 NRR E-mail Capture - Regarding Public Comment on Palisades Nuclear Plant License Transfer (Sierra Club Nuclear Free Michigan) ML21054A1812021-01-0606 January 2021 NRR E-mail Capture - (External_Sender) Regarding Public Comment on Palisades Request for Relief RR 5-8 ML20275A3432020-10-0101 October 2020 Verbal Authorization for Proposed Alternative (RR 5-8) Reactor Vessel Closure Head Penetration Repairs ML20272A0112020-09-26026 September 2020 Request for Additional Information - Palisades Relief Request RR 5-8 (Proposed Alternative) for Reactor Pressure Vessel Head Penetration Repairs ML20262G9622020-09-17017 September 2020 Acknowledgement to Mr. Muhich e-mail, Dated September 15, 2020 (e-mail) ML20241A1802020-08-27027 August 2020 NRR E-mail Capture - Palisades Nuclear Plant- Upcoming Steam Generator Tube Inservice Inspection ML20162A4522020-04-0808 April 2020 Lake Mich Level Correspondence with Ipotter ML19344C7162019-08-25025 August 2019 Response from NEIMA Local Community Advisory Board Questionnaire 08-25-2019 C Ferry ML19344C8072019-08-16016 August 2019 Scanned Response 09-29-2019 I Potter ML19226A2932019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Re License Amendment Request to Adopt TSTF-425, Revision 3 for the Palisades Nuclear Plant ML19226A2922019-08-0505 August 2019 NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Adopt TSTF-425 ML19122A4852019-04-29029 April 2019 NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise License Conditions Related to NFPA 805 Modifications ML19095A6572019-04-0505 April 2019 NRR E-mail Capture - Acceptance for Review of Application to Revise the Palisades Nuclear Plant License Renewed Facility Operation License Regarding Full Compliance Implementation Date for the Fire Protection Program ML19059A1782019-02-28028 February 2019 Acceptance Review Results for Relief Request No. EN-19-RR-1 to Use ASME Code Case N-831-1 for Entergy Fleet ML19059A0292019-02-27027 February 2019 NRR E-mail Capture - Acceptance Review Results for License Amendment Request to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules, for Entergy Fleet ML19009A5392019-01-0909 January 2019 NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a ML19009A5382018-12-12012 December 2018 NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a ML18337A1382018-11-30030 November 2018 NRR E-mail Capture - Request for Additional Information Related to Palisades Relief Request Number RR 5-7 ML18337A1352018-11-30030 November 2018 NRR E-mail Capture - Acceptance for Review of Application to Revise the Palisades Nuclear Plant License Renewed Facility Operation License Regarding Changes to the Fire Protection Plan ML18337A1402018-11-29029 November 2018 NRR E-mail Capture - Draft Request for Additional Information Related to Palisades Relief Request 5-7 ML18184A2402018-07-0303 July 2018 NRR E-mail Capture - Acceptance for Review of Application to Revise Technical Specification Surveillance Requirement 3.3.5.2a for the Diesel Generator Undervoltage Start ML18101A1132018-04-11011 April 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Alternative for Relevant Condition ML18081A2962018-03-22022 March 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Changes to Site Emergency Plan for Permanently Defueled Condition (CAC MG0198: EPID L-2017-LLA-0305) ML18059A8202018-02-28028 February 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Alternative for Relevant Condition ML17355A0092017-12-20020 December 2017 NRR E-mail Capture - Palisades Nuclear Plant: Acceptance Review for Relief Request No. RR 5-6 - Alternative to the Reexamination Frequency for a Relevant Condition ML17345A0142017-12-0808 December 2017 NRR E-mail Capture - Acceptance Review Results Entergy Request No. EN-17-RR-1 ML17338B1242017-11-30030 November 2017 NRR E-mail Capture - (External_Sender) Palisades Nuclear Plant Flood Hazard Reevaluation Report FHRR Staff Assessment Input ML17335A1042017-11-30030 November 2017 NRR E-mail Capture - Palisades Nuclear Plant - RAI Regarding Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition (CAC MG0021; EPID L-2017-LLA-0266) ML17317A0042017-11-0909 November 2017 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance Review for License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Transition License Condition 2024-02-01
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From: Chawla, Mahesh Sent: Friday, September 02, 2011 2:40 PM To: KUEMIN, JAMES L; GUSTAFSON, OTTO W Cc: Thomas, George; Khanna, Meena; Pascarelli, Robert; Lingam, Siva; Boyle, Patrick; Lee, Brian; Anderson, Shaun; Dozier, Jerry
Subject:
Request for Additional Information - Palisades - LAR to extend the Containment Type A Leak Rate Test Frequency to 15 years - ME5997 The NRC staff has reviewed the license amendment request (LAR) submitted by Entergy Nuclear Operations Inc. by letter dated April 6, 2011 (ADAMS Accession No. ML110970616).
The LAR requests to revise Technical Specification 5.5.14, Containment Leak Rate Testing Program, by replacing the reference to RG 1.163, Performance-Based Containment Leak-Test Program, with a reference to Topical Report NEI 94-01, Revision 2-A, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J, as the implementation document for the 10 CFR 50 Appendix J, Option B, performance-based containment leak rate testing program at the Palisades Nuclear Plant (PNP). This amendment would allow PNP to extend its performance-based containment integrated leakage rate test (ILRT or Type A test) interval up to 15 years. The staff has identified areas where additional information is needed to complete the review of the LAR.
Request for Additional Information:
RAI 1
In Section 4.3, Supplemental Inspection Requirements, of the license amendment request (LAR), Table 4.3-1, PLP Containment Inservice Inspection Periods (IWE/IWL), only provides the typical inspection schedule that is based on Subsection IWE of the ASME Code,Section XI, and applies to the Class MC containment metallic liner and its attachments. Please provide a similar schedule of inspections, in a tabular format similar to that of Table 4.3-1, for a typical 15-year interval (between the last Type A test in refuel outage 1R15 and the proposed next Type A test in refuel outage 1R24) that were or will be performed on the containment concrete surfaces in accordance with Subsection IWL and/or other and explain how it meets the requirements in Section 9.2.3.2 of NEI 94-01, Revision 2-A (i.e., one inspection prior to each Type A test and at least three (3) other inspections between Type A tests for a total of four (4) inspections, if the Type A test interval is extended to 15 years), and Condition 2 in Section 4.1 of the NRC Safety Evaluation for topical report NEI 94-01, Revision 2-A.
RAI 2
Condition 3 in Section 4.1 of the NRC Safety Evaluation (SE) for NEI 94-01, Revision 2-A, requires that licensees address the areas of the containment structure potentially subject to degradation (Refer to SE Section 3.1.3). Section 3.1.3 of the NRC SE, in part, states that licensees referencing NEI 94-01, Revision 2, in support of a request to amend their TS should also explore/consider such inaccessible degradation-susceptible areas in plant-specific inspections, using viable, commercially available NDE methods (such as, boroscopes, guided wave techniques, etc.- see Report ORNL/NRC/LTR-02/02, Inspection of Inaccessible Regions of Nuclear Power Plant Containment Metallic Pressure Boundaries, June 2002 (ADAMS Accession No.ML061230425) for recommendations) to support plant-specific evaluations.
The NRC staffs intent of this statement in the SER is that licensees should explore and consider NDE techniques, such as those discussed in the reference or other state-of-the-art
methods for inspections of inaccessible degradation-susceptible areas of the containment pressure boundary, in a proactive manner to support plant-specific evaluations of inaccessible areas, as these advanced technologies become commercially available and viable for implementation in practice in the future. The issue related to inaccessible areas is especially important in light of several instances of significant through-wall containment liner degradations (corrosion) that have been identified in the last decade in US operating nuclear plants, where the corrosion initiated at the inaccessible concrete-steel interface. While recognizing that these techniques may not be fully commercially viable at the present time, in order to fully address Condition 3 in Section 4.1 of the NRC SE, the licensee is requested to provide the following plant-specific information:
a) Identify the specific areas of the PNP containment pressure boundary (both concrete and steel) that are inaccessible and susceptible to degradation.
b) Acknowledge that NDE technologies (such as those described in the reference or others) would be explored in a proactive manner and considered in the future for the examination of inaccessible degradation-susceptible areas of the containment, as these technologies become commercially viable for implementation in practice. Include information of activities (such as participation in applicable cognizant owners groups, code committees, professional societies, etc. in the field) that the licensee is proactively participating in or plans to participate in for tracking applicable ongoing technology developments, operating experience and contributing towards achieving this goal.
c) Provide information of instances, if any, during implementation of the containment ISI program at PNP in accordance with IWE/IWL where existence of or potential for degraded conditions in inaccessible areas of the concrete containment structure and metallic liner were identified and evaluated based on conditions found in accessible areas, as required by 10 CFR 50.55a(b)(2)(viii)(E) and 10 CFR 50.55a(b)(2)(ix)(A). If there were any instances of such conditions, please discuss the findings and actions taken.
RAI 3
In order to adequately address Condition 4 in Section 4.1 of the NRC Safety Evaluation for Topical Report NEI 94-01, Revision 2-A, the licensee is requested to provide information that will demonstrate its understanding of: (a) the post-modification pressure testing and examination required to be performed prior to return to service following major containment modifications; and (b) the distinction between major and minor containment modifications. The NRC staff position is that the pressure testing performed prior to return to service following any major containment modification should demonstrate both structural integrity and leak-tight integrity of the containment. In responding to this RAI, please refer to Section 3.1.4 of the NRC Safety Evaluation for Topical Report NEI 94-01, Revision 2-A, and the regulatory condition in paragraph 10 CFR 50.55a(b)(2)(ix)(J) and its statement of considerations in the final rule published on June 21, 2011 in the Federal Register, Vol. 76, No. 119, pp 36232 thru 36279 (76 FR 36232-36270).
RAI 4
Please address whether bellows used on penetrations through containment pressure-retaining boundaries at PNP. If so, since degradation of bellows is a source for potential leakage, please provide information on their type (single-ply or two-ply), location, inspection, testing and operating experience with regard to detection of leakage through penetration bellows.
Reference:
Letter No. PNP 2011-018 dated April 6, 2011, from Thomas P. Kirwin, Entergy Nuclear Operations Inc - Palisades Nuclear Plant, to USNRC regarding License Amendment Request to Extend Containment Type A Leak Rate Test Frequency to 15 years (ADAMS Accession No. ML110970616)